DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 1
Text
Diablo Canyon Power Plant Units 1 and 2 Final Safety Analysis Report Update Revision 23 December 2016 Docket No. 50-275 Docket No. 50-323
DIABLO CANYON POWER PLANT UNITS 1 AND 2 FSAR UPDATE CONTENTS i Revision 23 December 2016 Chapter 1 - INTRODUCTION AND GENERAL DESCRIPTION OF PLANT 1.1 Introduction 1.2 General Plant Description 1.3 Comparison Tables 1.4 Identification of Agents and Contractors 1.5 Requirements for Further Technical Information 1.6 Material Incorporated by Reference
Tables for Chapter 1 Figures for Chapter 1
Chapter 2 - SITE CHARACTERISTICS 2.1 Geography and Demography 2.2 Nearby Industrial, Transportation, and Military Facilities
2.3 Meteorology 2.4 Hydrologic Engineering 2.5 Geology and Seismology
Tables for Chapter 2 Figures for Chapter 2
Chapter 3 - DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS 3.1 Conformance with AEC General Design Criteria 3.2 Classification of Structures, Systems, and Components 3.3 Wind and Tornado Loadings 3.4 Water Level (Flood) Design 3.5 Missile Protection 3.6 Protection Against Dynamic Effects Associated with the Postulated Rupture of Piping 3.7 Seismic Design 3.8 Design of PG&E Design Class I Structures 3.9 Mechanical Systems and Components 3.10 Seismic Design of PG&E Design Class I Instrumentation, HVAC, and Electrical Equipment 3.11 Environmental Design of Mechanical and Electrical Equipment
Tables for Chapter 3 Figures for Chapter 3 Appendices for Chapter 3
DIABLO CANYON POWER PLANT UNITS 1 AND 2 FSAR UPDATE CONTENTS ii Revision 23 December 2016 Chapter 4 - REACTOR 4.1 Summary Description 4.2 Mechanical Design 4.3 Nuclear Design 4.4 Thermal and Hydraulic Design
Tables for Chapter 4 Figures for Chapter 4
Chapter 5 - REACTOR COOLANT SYSTEM 5.1 Summary Description 5.2 Integrity of the Reactor Coolant Pressure Boundary 5.3 Thermal Hydraulic System Design 5.4 Reactor Pressure Vessel and Appurtenances 5.5 Component and Subsystem Design 5.6 Instrumentation Requirements
Tables for Chapter 5 Figures for Chapter 5
Chapter 6 - ENGINEERED SAFETY FEATURES 6.1 General 6.2 Containment Systems 6.3 Emergency Core Cooling System 6.4 Habitability Systems 6.5 Auxiliary Feedwater System
Tables for Chapter 6 Figures for Chapter 6 Appendices for Chapter 6
Chapter 7 - INSTRUMENTATION AND CONTROLS 7.1 Introduction 7.2 Reactor Trip System 7.3 Engineered Safety Features Actuation System 7.4 Systems Required for Safe Shutdown 7.5 Safety-Related Display Instrumentation 7.6 All Other Instrumentation Systems Required for Safety 7.7 Control Systems Not Required for Safety DIABLO CANYON POWER PLANT UNITS 1 AND 2 FSAR UPDATE CONTENTS iii Revision 23 December 2016 Chapter 7 (continued)
Tables for Chapter 7 Figures for Chapter 7
Chapter 8 - ELECTRIC POWER 8.1 Introduction 8.2 Offsite Power System 8.3 Onsite Power Systems
Tables for Chapter 8 Figures for Chapter 8 Appendices for Chapter 8
Chapter 9 - AUXILIARY SYSTEMS 9.1 Fuel Storage and Handling 9.2 Water Systems 9.3 Process Auxiliaries 9.4 Heating, Ventilation, and Air-Conditioning (HVAC) Systems 9.5 Other Auxiliary Systems Tables for Chapter 9 Figures for Chapter 9 Appendices for Chapter 9
Chapter 10 - STEAM AND POWER CONVERSION SYSTEM 10.1 Summary Description 10.2 Turbine-Generator 10.3 Main Steam System 10.4 Other Features of Steam and Power Conversion System
Tables for Chapter 10 Figures for Chapter 10
Chapter 11 - RADIOACTIVE WASTE MANAGEMENT 11 11.1 Radioactive Waste Management
Source Terms 11.2 Liquid RadWaste System 11.3 Gaseous RadWaste System 11.4 Process and Effluent Radiological Monitoring System DIABLO CANYON POWER PLANT UNITS 1 AND 2 FSAR UPDATE CONTENTS iv Revision 23 December 2016 Chapter 11 (continued) 11.5 Solid RadWaste System 11.6 Offsite Radiological Monitoring Program
Tables for Chapter 11 Figures for Chapter 11
Chapter 12 - RADIATION PROTECTION 12.1 Radiation Shielding
12.2 Ventilation 12.3 Radiation Protection Program
Tables for Chapter 12 Figures for Chapter 12
Chapter 13 - CONDUCT OF OPERATIONS 13.1 Organizational Structure 13.2 Training Program 13.3 Emergency Planning 13.4 Review and Audit 13.5 Plant Procedures and Programs 13.6 Plant Records 13.7 Physical Security
Tables for Chapter 13 Figures for Chapter 13
Chapter 14 - INITIAL TESTS AND OPERATION 14.1 Test Program 14.2 Augmentation of Applicant's Staff for Initial Tests and Operation 14.3 Postcommercial Operational Test Program
Tables for Chapter 14 Figures for Chapter 14
DIABLO CANYON POWER PLANT UNITS 1 AND 2 FSAR UPDATE CONTENTS v Revision 23 December 2016 Chapter 15 - ACCIDENT ANALYSES 15 Accident Analyses 15.1 Condition I - Normal Operation and Operational Transients (Initial Conditions) 15.2 Condition II - Faults of Moderate Frequency 15.3 Condition III - Infrequent Faults 15.4 Condition IV - Limiting Faults 15.5 Radiological Consequences of Plant Accidents Tables for Chapter 15 Figures for Chapter 15
Chapter 16 - TECHNICAL SPECIFICATIONS AND EQUIPMENT CONTROL GUIDELINES 16.1 Technical Specifications and Equipment Control Guidelines
Table for Chapter 16
Chapter 17 - QUALITY ASSURANCE 17.0 Quality Assurance Program
17.1 Organization
17.2 Quality Assurance Program 17.3 Design Control 17.4 Procurement Document Control 17.5 Instructions, Procedures, and Drawings 17.6 Document Control 17.7 Control of Purchased Material, Equipment, and Services 17.8 Identification and Control of Materials, Parts, and Components 17.9 Special Processes 17.10 Inspection 17.11 Test Control 17.12 Control of Measuring and Test Equipment 17.13 Handling, Storage, and Shipping 17.14 Inspection, Test, and Operating Status 17.15 Control of Nonconforming Conditions 17.16 Corrective Action 17.17 Quality Assurance Records
17.18 Audits
Table for Chapter 17 Figures for Chapter 17 DCPP UNITS 1 & 2 FSAR UPDATE LIST OF CURRENT PAGES Page No. Rev. Page No. Rev. Page No. Rev.
1 Revision 23 December 2016 CONTENTS i thru v 23
INDEX Removed in Rev 20
CHAPTER 1
i thru v 23 1.1-1 thru 1.1-3 23 1.2-1 thru 1.2-10 23
1.3-1 23 1.4-1 thru 1.4-3 23
1.5-1 23 1.6-1 thru 1.6-12 23 Table 1.3-1 -4 Sheets 23 Table 1.3-2 -4 Sheets 23 Table 1.4-1 -3 Sheets 23 Table 1.4-2 -3 Sheets 23 Table 1.4-3 -3 Sheets 23 Table 1.5-1 -3 Sheets 23 Table 1.6-1 -28 Sheets 23 Figure 1.2-1 18 Figure 1.2-2 11A
CHAPTER 2
i thru xx 23 2.1-1 thru 2.1-8 23 2.2-1 thru 2.2-5 23 2.3-1 thru 2.3-34 23 2.4-1 thru 2.4-24 23 2.5-1 thru 2.5-87 21 Table 2.1-1 22 Table 2.1-2 22 Table 2.1-3 22 Table 2.1-4 22 Table 2.1-5 22 Table 2.3-1 22 Table 2.3-2 22 Table 2.3-3 22 Table 2.3-4 22 Table 2.3-6 22 Table 2.3-7 22 Table 2.3-8 22 Table 2.3-9 22 Table 2.3-10 22 Table 2.3-11 22 Table 2.3-12 22 Table 2.3-13 22 Table 2.3-14 22 Table 2.3-15 22 Table 2.3-16 22 Table 2.3-17 22 Table 2.3-18 22 Table 2.3-19 22 Table 2.3-20 22 Table 2.3-21 22 Table 2.3-22 22 Table 2.3-23 22 Table 2.3-24 22 Table 2.3-25 22 Table 2.3-26 22 Table 2.3-27 22 Table 2.3-28 22 Table 2.3-29 22 Table 2.3-30 22 Table 2.3-31 22 Table 2.3-32 22 Table 2.3-33 22 Table 2.3-34 22 Table 2.3-35 22 Table 2.3-36 22 Table 2.3-37 22 Table 2.3-38 22 Table 2.3-39 22 Table 2.3-40 22 Table 2.3-41 -25 Sheets 22 Table 2.3-42 22 Table 2.3-43 22 Table 2.3-44 22 Table 2.3-45 22 Table 2.3-46 22 Table 2.3-47 22 Table 2.3-48 22 Table 2.3-49 22 Table 2.3-50 22 Table 2.3-51 22 Table 2.3-52 22 Table 2.3-53 22 Table 2.3-54 22 Table 2.3-55 22 Table 2.3-56 22 Table 2.3-57 22 Table 2.3-58 22 Table 2.3-59 22 Table 2.3-60 22 Table 2.3-61 22 Table 2.3-62 22 Table 2.3-63 22 Table 2.3-64 22 Table 2.3-65 22 Table 2.3-66 22 Table 2.3-67 22 Table 2.3-68 22 Table 2.3-69 22 Table 2.3-70 22 Table 2.3-71 22 Table 2.3-72 22 Table 2.3-73 22 Table 2.3-74 22 Table 2.3-75 22 Table 2.3-76 22 Table 2.3-77 22 Table 2.3-78 22 Table 2.3-79 22 Table 2.3-80 22 Table 2.3-81 22 Table 2.3-82 22 Table 2.3-83 22 Table 2.3-84 22 Table 2.3-85 22 Table 2.3-86 22 Table 2.3-87 22 Table 2.3-88 22 Table 2.3-89 22 Table 2.3-90 22 Table 2.3-91 22 Table 2.3-92 22 Table 2.3-93 22 Table 2.3-94 22 Table 2.3-95 22 Table 2.3-96 22 Table 2.3-97 22 Table 2.3-98 22 Table 2.3-99 22 Table 2.3-100 22 Table 2.3-101 22 Table 2.3-102 22 Table 2.3-103 22 Table 2.3-104 22 Table 2.3-105 22 Table 2.3-106 22 Table 2.3-107 22 Table 2.3-108 22 Table 2.3-109 22 Table 2.3-110 22 Table 2.3-111 22 Table 2.3-112 22 Table 2.3-113 22 Table 2.3-114 22 Table 2.3-115 22 Table 2.3-116 22 Table 2.3-117 22 Table 2.3-118 22 Table 2.3-119 22 Table 2.3-120 22 Table 2.3-121 22 Table 2.3-122 22 Table 2.3-123 22 Table 2.3-124 22 DCPP UNITS 1 & 2 FSAR UPDATE LIST OF CURRENT PAGES Page No. Rev. Page No. Rev. Page No. Rev.
2 Revision 23 December 2016 Table 2.3-125 22 Table 2.3-126 22 Table 2.3-127 22 Table 2.3-128 22 Table 2.3-129 22 Table 2.3-130 22 Table 2.3-131 22 Table 2.3-132 22 Table 2.3-133 22 Table 2.3-134 22 Table 2.3-135 22 Table 2.3-136 22 Table 2.3-137 22 Table 2.3-138 22 Table 2.3-139 22 Table 2.3-141 22 Table 2.3-142 22 Table 2.3-144 22 Table 2.4-1 22 Table 2.5-1 -43 Sheets 17 Table 2.5-2 -2 Sheets 11 Table 2.5-3 -2 Sheets 11 Figure 2.1-1 22 Figure 2.1-2 11 Figure 2.1-3 22 Figure 2.1-4 22 Figure 2.1-5 22 Figure 2.1-6 22 Figure 2.1-7 22 Figure 2.1-8 22 Figure 2.1-9 22 Figure 2.1-14 22 Figure 2.1-15 22 Figure 2.3-1 23 Figure 2.3-2 23 Figure 2.3-3 11 Figure 2.3-4 20 Figure 2.4-1 -2 Sheets 11 Figure 2.4-2 11 Figure 2.4-3 11 Figure 2.4-4 -3 Sheets 11 Figure 2.4-5 -3 Sheets 11 Figure 2.4-6 -2 Sheets 11 Figure 2.4-9 11 Figure 2.5-1 11 Figure 2.5-2 11 Figure 2.5-3 11 Figure 2.5-4 11 Figure 2.5-5 -2 Sheets 11 Figure 2.5-6 11 Figure 2.5-7 11 Figure 2.5-8 11 Figure 2.5-9 11 Figure 2.5-10 11 Figure 2.5-11 11 Figure 2.5-12 11 Figure 2.5-13 11 Figure 2.5-14 11 Figure 2.5-15 11 Figure 2.5-16 11 Figure 2.5-17 11 Figure 2.5-18 11 Figure 2.5-19 11 Figure 2.5-20 11 Figure 2.5-21 11 Figure 2.5-22 11 Figure 2.5-23 11 Figure 2.5-24 11 Figure 2.5-25 11 Figure 2.5-26 11 Figure 2.5-27 11 Figure 2.5-28 11 Figure 2.5-29 11 Figure 2.5-30 11 Figure 2.5-31 11 Figure 2.5-32 11 Figure 2.5-33 21 Figure 2.5-34 21 Figure 2.5-35 23 Figure 2.5-36 21
CHAPTER 3
i thru xlii 23 3.1-1 thru 3.1-48 23 3.2-1 thru 3.2-17 23 3.3-1 thru 3.3-32 23 3.4-1 thru 3.4-4 23 3.5-1 thru 3.5-17 23 3.6-1 thru 3.6-30 23 3.7-1 thru 3.7-53 23 3.8-1 thru 3.8-98 23 3.9-1 thru 3.9-40 23 3.10-1 thru 3.10-40 23 3.11-1 thru 3.11-13 23 Table 3.1-1 -2 Sheets 23 Table 3.1-2 -6 Sheets 23 Table 3.2-1 -2 Sheets 22 Table 3.2-2 -4 Sheets 22 Table 3.2-3 -59 Sheets 23 Table 3.2 2 Sheets 22 Table 3.3-1 23 Table 3.3-2 -4 Sheets 23 Table 3.3-3 -3 Sheets 23 Table 3.3-4 -2 Sheets 23 Table 3.3-5 -2 Sheets 23 Table 3.3-6 23 Table 3.5-2 11 Table 3.5-3 11 Table 3.5-4 11 Table 3.5-5 22 Table 3.5-6 11 Table 3.6-1 -9 Sheets 11 Table 3.6-2 -3 Sheets 19 Table 3.6-6 11 Table 3.7-1 11 Table 3.7-1A 11 Table 3.7-1B 11 Table 3.7-1C 11 Table 3.7-2 11 Table 3.7-3 11 Table 3.7-4 11 Table 3.7-5 11 Table 3.7-6 11 Table 3.7-7 11 Table 3.7-8 11 Table 3.7-8A 11 Table 3.7-8B 11 Table 3.7-8C 22 Table 3.7-8D 22 Table 3.7-8E 11 Table 3.7-8F 11 Table 3.7-8G 11 Table 3.7-8H 11 Table 3.7-8I 11 Table 3.7-8J 11 Table 3.7-8K 11 Table 3.7-8L -2 Sheets 21 Table 3.7-8M -2 Sheets 21 Table 3.7-8N -2 Sheets 21 Table 3.7-8O 11 Table 3.7-8P 23 Table 3.7-9 22 Table 3.7-10 22 Table 3.7-11 11 Table 3.7-11A 11 Table 3.7-11B 11 Table 3.7-12 11 Table 3.7-13 11 Table 3.7-14 11 Table 3.7-15 11 Table 3.7-16 11 Table 3.7-17 11 Table 3.7-18 11 Table 3.7-19 11 Table 3.7-20 11 Table 3.7-21 11 Table 3.7-22 22 Table 3.7-23 11 Table 3.7-23A -2 Sheets 11 Table 3.7-23B 11 Table 3.7-23C -2 Sheets 11 DCPP UNITS 1 & 2 FSAR UPDATE LIST OF CURRENT PAGES Page No. Rev. Page No. Rev. Page No. Rev.
3 Revision 23 December 2016 Table 3.7-23D 11 Table 3.7-23E 22 Table 3.7-23F 22 Table 3.7-23G 11 Table 3.7-23H 11 Table 3.7-23I 11 Table 3.7-23J 11 Table 3.7-24 19 Table 3.8-1 -2 Sheets 23 Table 3.8-2 -5 Sheets 23 Table 3.8-3 -10 Sheets 23 Table 3.8-4 11 Table 3.8-5 -3 Sheets 11 Table 3.8-5A 11 Table 3.8-5B 12 Table 3.8-6 -3 Sheets 23 Table 3.8-6A 21 Table 3.8-6B 11 Table 3.8-7 22 Table 3.8-8 11 Table 3.8-9 23 Table 3.8-10 11 Table 3.8-11 11 Table 3.8-12 11 Table 3.8-13 11 Table 3.8-14 11 Table 3.8-15 11 Table 3.8-16 11 Table 3.8-17 11 Table 3.8-18 11 Table 3.8-19 11 Table 3.8-20 23 Table 3.8-21 11 Table 3.8-22 11 Table 3.8-23 11 Table 3.8-23A 11 Table 3.8-24 23 Table 3.8-25 11 Table 3.8-26 11 Table 3.8-27 11 Table 3.8-27A 11 Table 3.8-28 11 Table 3.9-1 -2 Sheets 22 Table 3.9-2 -3 Sheets 22 Table 3.9-3 -2 Sheets 23 Table 3.9-4 -3 Sheets 22 Table 3.9-5 -2 Sheets 22 Table 3.9-6 -3 Sheets 22 Table 3.9-7 -2 Sheets 22 Table 3.9-8 -3 Sheets 22 Table 3.9-9 -25 Sheets 23 Table 3.9-10 11 Table 3.9-11 -2 Sheets 22 Table 3.9-12 -5 Sheets 22 Table 3.10-1 -2 Sheets 23 Table 3.10-2 -4 Sheets 23 Table 3.10-3 -31 Sheets 22 Figure 3.3-1 13 Figure 3.3-2 13 Figure 3.3-3 11 Figure 3.3-4 -2 Sheets 11 Figure 3.5-1 20 Figure 3.5-2 11 Figure 3.6-1 11 Figure 3.6-3 11 Figure 3.6-3A 11 Figure 3.6-3B 11 Figure 3.6-3C 11 Figure 3.6-4 12 Figure 3.6-16 11 Figure 3.5-17 11 Figure 3.6-18 11 Figure 3.6-19 11 Figure 3.6-20 11 Figure 3.6-21 11 Figure 3.6-22 11 Figure 3.6-23 11 Figure 3.6-24 12 Figure 3.6-25 11 Figure 3.6-26 22 Figure 3.6-28 22 Figure 3.6-29 22 Figure 3.6-30 22 Figure 3.6-31 11 Figure 3.6-32 11 Figure 3.6-33 11 Figure 3.6-34 11 Figure 3.6-35 11 Figure 3.6-36 11 Figure 3.6-37 11 Figure 3.6-38 12 Figure 3.6-39 11 Figure 3.6-40 12 Figure 3.6-41 11 Figure 3.6-42 12 Figure 3.6-43 22 Figure 3.6-44 22 Figure 3.7-1 11 Figure 3.7-2 11 Figure 3.7-3 11 Figure 3.7-4 11 Figure 3.7-4A 11 Figure 3.7-4B 11 Figure 3.7-4C 11 Figure 3.7-4D 11 Figure 3.7-4E 11 Figure 3.7-4F 11 Figure 3.7-4G 11 Figure 3.7-4H 11 Figure 3.7-4I 11 Figure 3.7-4J 11 Figure 3.7-4K 11 Figure 3.7-4L 11A Figure 3.7-4M 11A Figure 3.7-4N 11 Figure 3.7-4O 11 Figure 3.7-4P 11 Figure 3.7-4Q 11 Figure 3.7-4R 11 Figure 3.7-4S 11A Figure 3.7-4T 11 Figure 3.7-5 11 Figure 3.7-5A 11 Figure 3.7-5B 11 Figure 3.7-5C 11 Figure 3.7-5D 11 Figure 3.7-5E 11 Figure 3.7-6 11 Figure 3.7-7 11 Figure 3.7-7A 21 Figure 3.7-8 11 Figure 3.7-9 11 Figure 3.7-10 11 Figure 3.7-11 11 Figure 3.7-12 11 Figure 3.7-12A 11 Figure 3.7-12B 11 Figure 3.7-12C 11 Figure 3.7-12D 11 Figure 3.7-12E 11 Figure 3.7-12F 11 Figure 3.7-12G 11 Figure 3.7-12H 11 Figure 3.7-12I 11 Figure 3.7-12J 11 Figure 3.7-12K 11 Figure 3.7-12L 11 Figure 3.7-12M 11 Figure 3.7-12N 11 Figure 3.7-12O 11 Figure 3.7-12P 11 Figure 3.7-12Q 11 Figure 3.7-12R 11 Figure 3.7-12S 11 Figure 3.7-13 11 Figure 3.7-13A 11 Figure 3.7-13B 11 Figure 3.7-14 11 Figure 3.7-15 11 Figure 3.7-15A 11 Figure 3.7-15B 11 Figure 3.7-15C 11 DCPP UNITS 1 & 2 FSAR UPDATE LIST OF CURRENT PAGES Page No. Rev. Page No. Rev. Page No. Rev.
4 Revision 23 December 2016 Figure 3.7-15D 11 Figure 3.7-15E 11 Figure 3.7-15F 11 Figure 3.7-15G 22 Figure 3.7-15H 11 Figure 3.7-15I 11 Figure 3.7-16 11 Figure 3.7-17 11 Figure 3.7-18 11 Figure 3.7-19 11 Figure 3.7-20 11 Figure 3.7-21 11 Figure 3.7-21A 11 Figure 3.7-21B 11 Figure 3.7-21C 11 Figure 3.7-21D 11 Figure 3.7-21E 11 Figure 3.7-21F 11 Figure 3.7-21G 11 Figure 3.7-21H 11 Figure 3.7-21I 11 Figure 3.7-22 11 Figure 3.7-23 11 Figure 3.7-24 11 Figure 3.7-25 11 Figure 3.7-25A 11 Figure 3.7-25B 11 Figure 3.7-25C 11 Figure 3.7-25D 11 Figure 3.7-25E 11 Figure 3.7-25F 11 Figure 3.7-25G 11 Figure 3.7-25H 11 Figure 3.7-25I 11 Figure 3.7-25J 11 Figure 3.7-25K 11 Figure 3.7-25L 11 Figure 3.7-25M 11 Figure 3.7-25N 11 Figure 3.7-25O 11 Figure 3.7-25P 11 Figure 3.7-25Q 11 Figure 3.7-25R 11 Figure 3.7-25S 11 Figure 3.7-25T 11 Figure 3.7-26 11 Figure 3.7-27 11 Figure 3.7-27A 20 Figure 3.7-27B 20 Figure 3.7-27C 19 Figure 3.7-27D 20 Figure 3.7-27E 20 Figure 3.7-27F 23 Figure 3.7-28 11 Figure 3.7-29 11 Figure 3.8-1 23 Figure 3.8-2 23 Figure 3.8-3 23 Figure 3.8-4 23 Figure 3.8-5 23 Figure 3.8-6 23 Figure 3.8-7 23 Figure 3.8-8 23 Figure 3.8-9 23 Figure 3.8-10 23 Figure 3.8-11 23 Figure 3.8-12 23 Figure 3.8-13 23 Figure 3.8-14 23 Figure 3.8-15 23 Figure 3.8-21 -2 Sheets 11 Figure 3.8-22 -2 Sheets 11 Figure 3.8-27 11 Figure 3.8-28 11 Figure 3.8-29 11 Figure 3.8-30 11 Figure 3.8-31 11 Figure 3.8-32 11 Figure 3.8-33 11 Figure 3.8-34 11 Figure 3.8-35 11 Figure 3.8-37 11 Figure 3.8-38 11 Figure 3.8-39 11 Figure 3.8-40 11 Figure 3.8-41 11 Figure 3.8-42 11 Figure 3.8-43 11 Figure 3.8-44 11 Figure 3.8-60 11 Figure 3.8-61 11 Figure 3.8-62 11 Figure 3.8-63 11 Figure 3.8-64 11 Figure 3.8-66 11 Figure 3.8-67 11 Figure 3.8-68 11 Figure 3.8-69 11 Figure 3.8-70 11 Figure 3.8-71 11 Figure 3.8-75 11 Figure 3.8-76 11 Figure 3.8-77 11 Figure 3.8-78 11 Figure 3.8-79 11 Figure 3.8-80 11 Figure 3.8-81 11 Figure 3.8-82 11 Figure 3.9-1 11 Figure 3.9-2 11 Figure 3.9-3 11 Figure 3.9-4 11 Appendix 3.1A-1 thru 41 23
CHAPTER 4
i thru xi 23 4.1-1 thru 4.1-3 23 4.2-1 thru 4.2-60 23 4.3-1 thru 4.3-40 23 4.4-1 thru 4.4-42 23 Table 4.1-1 -7 Sheets 23 Table 4.1-2 -3 Sheets 23 Table 4.1-3 12 Table 4.3-1 -2 Sheets 23 Table 4.3-2 23 Table 4.3-3 23 Table 4.3-4 23 Table 4.3-5 11 Table 4.3-6 11 Table 4.3-7 11 Table 4.3-8 11 Table 4.3-9 11 Table 4.3-10 11 Table 4.3-11 23 Table 4.4-1 23 Table 4.4-2 23 Table 4.4-3 23 Table 4.4-4 23 Figure 4.2-1 11 Figure 4.2-2 11 Figure 4.2-3 11 Figure 4.2-4 11 Figure 4.2-5 23 Figure 4.2-6 23 Figure 4.2-7 23 Figure 4.2-8 23 Figure 4.2-9 11 Figure 4.2-10 11 Figure 4.2-11 11 Figure 4.2-12 11 Figure 4.2-13 11 Figure 4.2-14 11 Figure 4.2-15 11 Figure 4.2-16 14 Figure 4.2-17 14 Figure 4.2-18a 11 Figure 4.2-21 11 Figure 4.2-22 11 Figure 4.2-23 20 Figure 4.2-24 20 Figure 4.2-25 23 DCPP UNITS 1 & 2 FSAR UPDATE LIST OF CURRENT PAGES Page No. Rev. Page No. Rev. Page No. Rev.
5 Revision 23 December 2016 Figure 4.2-26 11 Figure 4.3-1 11 Figure 4.3-2 23 Figure 4.3-3 11 Figure 4.3-4 11 Figure 4.3-5 11 Figure 4.3-6 11 Figure 4.3-7 11 Figure 4.3-8 11 Figure 4.3-9 11 Figure 4.3-10 11 Figure 4.3-11 11 Figure 4.3-12 11 Figure 4.3-13 11 Figure 4.3-14 11 Figure 4.3-15 11 Figure 4.3-16 11 Figure 4.3-17 11 Figure 4.3-21 23 Figure 4.3-22 23 Figure 4.3-23 11 Figure 4.3-25 11 Figure 4.3-26 11 Figure 4.3-27 11 Figure 4.3-28 11 Figure 4.3-29 11 Figure 4.3-30 11 Figure 4.3-31 11 Figure 4.3-32 11 Figure 4.3-33 11 Figure 4.3-34 11 Figure 4.3-35 11 Figure 4.3-36 11 Figure 4.3-37 11 Figure 4.3-38 11 Figure 4.3-39 11 Figure 4.3-40 11 Figure 4.3-41 11 Figure 4.3-42 11 Figure 4.3-43 11 Figure 4.3-44 11 Figure 4.3-45 11 Figure 4.3-46 11 Figure 4.3-47 11 Figure 4.4-1 11 Figure 4.4-2 11 Figure 4.4-3 11 Figure 4.4-4 11 Figure 4.4-5 11 Figure 4.4-6 11 Figure 4.4-7 11 Figure 4.4-8 11 Figure 4.4-9 11 Figure 4.4-10 11 Figure 4.4-11 11 Figure 4.4-12 11 Figure 4.4-13 11 Figure 4.4-14 11 Figure 4.4-15 11 Figure 4.4-16 11 Figure 4.4-17 11 Figure 4.4-18 11 Figure 4.4-19 23 Figure 4.4-20 23 CHAPTER 5
i thru xx 23 5.1-1 thru 5.1-29 23 5.2-1 thru 5.2-88 23 5.3-1 thru 5.3-2 23 5.4-1 thru 5.4-7 23 5.5-1 thru 5.5-55 23 5.6-1 thru 5.6-4 23 Table 5.0-1 -4 Sheets 23 Table 5.1-1 -2 Sheets 22 Table 5.2-1 -2 Sheets 23 Table 5.2-2 -2 Sheets 23 Table 5.2-3 20 Table 5.2-4 -2 Sheets 23 Table 5.2-5 -2 Sheets 23 Table 5.2-6 -2 Sheets 23 Table 5.2-6a 22 Table 5.2-7 23 Table 5.2-8 -2 Sheets 23 Table 5.2-8a 23 Table 5.2-9 -3 Sheets 23 Table 5.2-10 11A Table 5.2-11 23 Table 5.2-12 -2 Sheets 23 Table 5.2-13 19 Table 5.2-14 19 Table 5.2-15 12 Table 5.2-16 -4 Sheets 23 Table 5.2-17A 23 Table 5.2-17B 23 Table 5.2-18A 23 Table 5.2-18B 21 Table 5.2-19A 15 Table 5.2-19B 23 Table 5.2-20A 15 Table 5.2-20B 15 Table 5.2-21A 20 Table 5.2-21B 20 Table 5.2-22 21 Table 5.2-23 16 Table 5.4-1 23 Table 5.4-2 23 Table 5.5-1 23 Table 5.5-2 23 Table 5.5-3 -2 Sheets 23 Table 5.5-5 -2 Sheets 23 Table 5.5-6 23 Table 5.5-7 23 Table 5.5-8 14 Table 5.5-9 23 Table 5.5-10 -2 Sheets 12 Table 5.5-11 18 Table 5.5-12 12 Table 5.5-13 23 Table 5.5-14 11 Table 5.5-15 11 Table 5.5-16 23 Table 5.5-17 20 Figure 5.1-2 22 Figure 5.1-2a 22 Figure 5.2-1 11 Figure 5.2-2 23 Figure 5.2-2A 23 Figure 5.2-3 19 Figure 5.2-4 11 Figure 5.2-7 21 Figure 5.2-8 11 Figure 5.2-9 11 Figure 5.2-10 11 Figure 5.2-11 11 Figure 5.2-12 11 Figure 5.2-13 11 Figure 5.2-14 19 Figure 5.2-15 11 Figure 5.2-16 11 Figure 5.2-17 11 Figure 5.2-18 11 Figure 5.2-19 11 Figure 5.3-1 21 Figure 5.4-1 20 Figure 5.4-2 20 Figure 5.4-3 22 Figure 5.5-1 11 Figure 5.5-2 11 Figure 5.5-3 11 Figure 5.5-4 19 Figure 5.5-8 11 Figure 5.5-9 11 Figure 5.5-10 19 Figure 5.5-11 18 Figure 5.5-12 11 Figure 5.5-14 20 Figure 5.5-18 19
DCPP UNITS 1 & 2 FSAR UPDATE LIST OF CURRENT PAGES Page No. Rev. Page No. Rev. Page No. Rev.
6 Revision 23 December 2016 CHAPTER 6 i thru xxiii 23 6.1-1 thru 6.1-5 22 6.2-1 thru 6.2-109 23 6.3-1 thru 6.3-68 23 6.4-1 thru 6.4-14 23 6.5-1 thru 6.5-25 23 Table 6.1-1 -12 Sheets 22 Table 6.2-25 22 Table 6.2-26 -3 Sheets 22 Table 6.2-27 22 Table 6.2-29 22 Table 6.2-30 11 Table 6.2-36 22 Table 6.2-37 11 Table 6.2-38 22 Table 6.2-39 -24 Sheets 23 Table 6.2-40 -2 Sheets 22 Table 6.2-41 14 Table 6.2-42 -2 Sheets 14 Table 6.2-43 22 Table 6.2-44 22 Table 6.2-45 22 Table 6.2-47 -2 Sheets 11 Table 6.2-48 -2 Sheets 19 Table 6.2-57 -2 Sheets 23 Table 6.2-58 -2 Sheets 23 Table 6.2-59 -2 Sheets 23 Table 6.2-60 -2 Sheets 23 Table 6.2-61 -2 Sheets 23 Table 6.2-62 23 Table 6.2-63 -3 Sheets 23 Table 6.2-64 23 Table 6.2-65 23 Table 6.2-66 23 Table 6.2-67 23 Table 6.3-1 -3 Sheets 22 Table 6.3-2 12 Table 6.3-3 -2 Sheets 12 Table 6.3-5 -6 Sheets 20 Table 6.3-6 12 Table 6.3-7 -4 Sheets 23 Table 6.3-8 12 Table 6.3-9 11 Table 6.3-10 11 Table 6.3-11 18 Table 6.3-12 -2 Sheets 16 Table 6.3-13 -3 Sheets 22 Table 6.3-14 22 Table 6.5-1 -2 Sheets 23 Table 6.5-2 -2 Sheets 23 Table 6.5-3 22 Figure 6.2-10 11 Figure 6.2-12 11 Figure 6.2-13 22 Figure 6.2-14 12 Figure 6.2-15 11 Figure 6.2-16 12 Figure 6.2-17 11 Figure 6.2-18 -2 Sheets 11 Figure 6.2-19, Sheet 1 11 Figure 6.2-19, Sheet 2 11 Figure 6.2-19, Sheet 3 11 Figure 6.2-19, Sheet 4 22 Figure 6.2-19, Sheet 5 22 Figure 6.2-19, Sheet 5A 22 Figure 6.2-19, Sheet 6 20 Figure 6.2-19, Sheet 7 21 Figure 6.2-19, Sheet 8 20 Figure 6.2-19, Sheet 8A 20 Figure 6.2-19, Sheet 9 21 Figure 6.2-19, Sheet 10 21 Figure 6.2-19, Sheet 11 11 Figure 6.2-19, Sheet 12 22 Figure 6.2-19, Sheet 13 20 Figure 6.2-19, Sheet 13A 20 Figure 6.2-19, Sheet 14 22 Figure 6.2-19, Sheet 15 11 Figure 6.2-19, Sheet 16 21 Figure 6.2-19, Sheet 17 22 Figure 6.2-19, Sheet 18 11 Figure 6.2-19, Sheet 19 11 Figure 6.2-19, Sheet 20 11 Figure 6.2-19, Sheet 21 19 Figure 6.2-19, Sheet 21A 19 Figure 6.2-19, Sheet 22 18 Figure 6.2-19, Sheet 23 21 Figure 6.2-19, Sheet 24 16 Figure 6.2-19, Sheet 25 21 Figure 6.2-20 11 Figure 6.2-21 11 Figure 6.2-22 16 Figure 6.2-23 11 Figure 6.2-24 11 Figure 6.2-25 14 Figure 6.2-26 14 Figure 6.2-27 14 Figure 6.2-28 14 Figure 6.2-29 14 Figure 6.2-53 23 Figure 6.2-54 23 Figure 6.2-55 23 Figure 6.2-56 23 Figure 6.2-57 23 Figure 6.2-58 23 Figure 6.2-59 23 Figure 6.2-60 23 Figure 6.2-61 23 Figure 6.2-62 23 Figure 6.2-63 23 Figure 6.2-64 23 Figure 6.2-65 23 Figure 6.2-66 23 Figure 6.2-67 23 Figure 6.2-68 23 Figure 6-2-69 23 Figure 6.2-70 23 Figure 6.2-71 23 Figure 6.2-72 23 Figure 6.2-73 23 Figure 6.2-74 23 Figure 6.3-1 11 Figure 6.3-2 18 Figure 6.3-3 11 Figure 6.3-4 22 Figure 6.3-5 20 Figure 6.5-3, Sheet 1 12 Figure 6.5-3, Sheet 2 20 Appendix 6.2D-1 thru 32 23 Table 6.2D-1 23 Table 6.2D-2 18 Table 6.2D-3 -4 Sheets 23 Table 6.2D-4 23 Table 6.2D-5 23 Table 6.2D-6 -5 Sheets 23 Table 6.2D-7-5 Sheets 23 Table 6.2D-8 -2 Sheets 23 Table 6.2D-9 -3 Sheets 23 Table 6.2D-10 22 Table 6.2D-11 23 Table 6.2D-12 23 Table 6.2D-13 23 Table 6.2D-15 23 Table 6.2D-17 -2 Sheets 23 Table 6.2D-18 18 Table 6.2D-19 18 Table 6.2D-20 22 Table 6.2D-21 23 Table 6.2D-22 23 Table 6.2D-23 23 Table 6.2D-24 23 Figure 6.2D-1 23 Figure 6.2D-2 23 Figure 6.2D-3 18 Figure 6.2D-4 22 Figure 6.2D-5 18 Figure 6.2D-6 23 Figure 6.2D-7 23 Figure 6.2D-9 23 Figure 6.2D-10 23
DCPP UNITS 1 & 2 FSAR UPDATE LIST OF CURRENT PAGES Page No. Rev. Page No. Rev. Page No. Rev.
7 Revision 23 December 2016
CHAPTER 7
i thru xvii 23 7.1-1 thru 7.1-9 22 7.2-1 thru 7.2-51 23 7.3-1 thru 7.3-32 23 7.4-1 thru 7.4-17 23 7.5-1 thru 7.5-26 23 7.6-1 thru 7.6-11 23 7.7-1 thru 7.7-34 23 Table 7.1-1 -3 Sheets 22 Table 7.2-1 -3 Sheets 20 Table 7.2-2 -2 Sheets 12 Table 7.3-1 11 Table 7.3-2 -2 Sheets 11 Table 7.3-3 -2 Sheets 23 Table 7.5-1 -4 Sheets 16 Table 7.5-2 -4 Sheets 17 Table 7.5-3 -8 Sheets 18 Table 7.5-4 -2 Sheets 22 Table 7.5-5 -2 Sheets 23 Table 7.5-6 -14 Sheets 22 Table 7.7-1 -2 Sheets 23 Figure 7.2-2 22 Figure 7.2-4 11 Figure 7.2-5 11 Figure 7.2-6 -2 Sheets 11 Figure 7.5-1 19 Figure 7.5-1B 19 Figure 7.5-2 12 Figure 7.7-1 11 Figure 7.7-2 16 Figure 7.7-3 11 Figure 7.7-4 16 Figure 7.7-5 21 Figure 7.7-8 21 Figure 7.7-9 11
CHAPTER 8
i thru vii 23 8.1-1 thru 8.1-6 23 8.2-1 thru 8.2-16 23 8.3-1 thru 8.3-89 23 Table 8.1-1 -4 Sheets 21 Table 8.3-1 -3 Sheets 23 Table 8.3-2 18 Table 8.3-3 23 Table 8.3-4 23 Table 8.3-5 23 Table 8.3-8 -5 Sheets 12 Table 8.3-9 11 Table 8.3-10 11 Table 8.3-11 12 Table 8.3-12 23 Figure 8.1-2 22 Figure 8.3-21 11 Figure 8.3-22 11 Figure 8.3-23 11 Figure 8.3-24 11 Figure 8.3-25 11 Figure 8.3-26 11 Figure 8.3-27 11 Figure 8.3-28 11 Appendix 8.3B-1 thru 2 21 Appendix 8.3C-1 thru 3 15
CHAPTER 9
i thru xv 23 9.1-1 thru 9.1-69 23 9.2-1 thru 9.2-64 23 9.3-1 thru 9.3-98 23 9.4-1 thru 9.4-88 23 9.5-1 thru 9.5-40 23 Table 9.1-1 -2 Sheets 22 Table 9.1-2 -3 Sheets 16 Table 9.2-1 12 Table 9.2-2 21 Table 9.2-3 22 Table 9.2-4 20 Table 9.2-5 -2 Sheets 20 Table 9.2-6 15 Table 9.2-7 -3 Sheets 23 Table 9.2-9 -3 Sheets 23 Table 9.3-1 -2 Sheets 23 Table 9.3-2 11 Table 9.3-5 22 Table 9.3-6 -8 Sheets 22 Table 9.3-7 -2 Sheets 20 Table 9.3-8 14 Table 9.4-1 -2 Sheets 23 Table 9.4-2 -5 Sheets 22 Table 9.4-5 22 Table 9.4-6 -2 Sheets 22 Table 9.4-7 22 Table 9.4-8 -3 Sheets 22 Table 9.4-9 13 Table 9.4-10 -2 Sheets 22 Table 9.4-11 20 Table 9.4-12 22 Table 9.5-1 18 Table 9.5-2 11A Figure 9.1-1 22 Figure 9.1-2 22 Figure 9.1-2A 16 Figure 9.1-2B 15 Figure 9.1-4 19 Figure 9.1-5 18 Figure 9.1-6 19 Figure 9.1-7 19 Figure 9.1-8 11 Figure 9.1-9 11 Figure 9.1-10 11 Figure 9.1-11 11 Figure 9.1-12 11 Figure 9.1-12a 11 Figure 9.1-13 11 Figure 9.1-14 11 Figure 9.1-15 20 Figure 9.1-16 11 Figure 9.1-17 11 Figure 9.1-18 11 Figure 9.1-19 19 Figure 9.1-20 19 Figure 9.1-21 19 Figure 9.1-24 19 Figure 9.2-2 12 Figure 9.2-3 12 Figure 9.3-5 11 Figure 9.4-4 20 Figure 9.4-5 11 Figure 9.4-6 16 Figure 9.4-7 22 Figure 9.4-11 11 Figure 9.5-1 17 Figure 9.5-2 17 Figure 9.5-3 14 Figure 9.5-5 23 Figure 9.5-6 23
Appendix 9.5A-1 thru 624 23 Appendix 9.5B-1 thru 43 15 Appendix 9.5C-1 thru 6 15 Appendix 9.5D-1 thru 6 22 Appendix 9.5E-1 thru 2 15 Appendix 9.5F-1 thru 2 16 Figure 9.5F-20A 11 Figure 9.5F-20B 11 Figure 9.5F-20C 11 Figure 9.5F-20D 11 Figure 9.5F-21 11 Figure 9.5F-22 11 Figure 9.5F-23 11 Figure 9.5F-24 11 Figure 9.5F-25 11 Figure 9.5F-26 11 Figure 9.5F-27 11 DCPP UNITS 1 & 2 FSAR UPDATE LIST OF CURRENT PAGES Page No. Rev. Page No. Rev. Page No. Rev.
8 Revision 23 December 2016 Figure 9.5F-28 11 Figure 9.5F-29 11 Figure 9.5F-30 11 Figure 9.5F-31 11 Figure 9.5F-32 11 Figure 9.5F-33 11 Appendix 9.5G-1 23
Table 9.5G-1 -10 Sheets 23
Table 9.5G-2 -10 Sheets 23 Appendix 9.5H-i 23 Appendix 9.5H-1 thru 20 23
CHAPTER 10
i thru vii 23 10.1-1 thru 10.1-2 23 10.2-1 thru 10.2-12 23 10.3-1 thru 10.3-18 23 10.4-1 thru 10.4-48 23 Table 10.0-1 -5 Sheets 23 Table 10.1-1 23 Table 10.1-2 19 Table 10.3-1 22 Table 10.3-2 23 Table 10.4-1 22 Figure 10.2-1 18 Figure 10.3-6 11 Figure 10.4-2 11 Figure 10.4-3 11
CHAPTER 11
i thru xxi 23 11-1 thru 11-2 23 11.1-1 thru 11.1-7 23 11.2-1 thru 11.2-26 23 11.3-1 thru 11.3-16 23 11.4-1 thru 11.4-27 23 11.5-1 thru 11.5-11 23 11.6-1 thru 11.6-6 23 Table 11.0-1 -4 Sheets 23 Table 11.1-1 23 Table 11.1-2 23 Table 11.1-3 23 Table 11.1-4 23 Table 11.1-5 23 Table 11.1-6 23 Table 11.1-7 23 Table 11.1-8 23 Table 11.1-9 23 Table 11.1-10 23 Table 11.1-11 23 Table 11.1-12 23 Table 11.1-13 23 Table 11.1-14 23 Table 11.1-15 23 Table 11.1-16 23 Table 11.1-17 23 Table 11.1-18 23 Table 11.1-19 23 Table 11.1-20 23 Table 11.1-21 23 Table 11.1-22 23 Table 11.1-23 23 Table 11.1-24 23 Table 11.1-25 23 Table 11.1-26 23 Table 11.1-27 23 Table 11.1-28 23 Table 11.1-29 23 Table 11.1-30 23 Table 11.1-31 23 Table 11.2-1 -2 Sheets 23 Table 11.2-2 23 Table 11.2-3 -2 Sheets 23 Table 11.2-4 -2 Sheets 23 Table 11.2-5 -4 Sheets 23 Table 11.2-6 -2 Sheets 23 Table 11.2-7 -2 Sheets 23 Table 11.2-8 -5 Sheets 23 Table 11.2-9 -5 Sheets 23 Table 11.2-10 -3 Sheets 23 Table 11.2-11 23 Table 11.2-13 23 Table 11.2-14 23 Table 11.2-15 23 Table 11.2-16 -2 Sheets 23 Table 11.2-17 23 Table 11.2-18 23 Table 11.2-19 23 Table 11.2-20 23 Table 11.2-21 -2 Sheets 23 Table 11.2-22 23 Table 11.2-23 23 Table 11.2-24 -2 Sheets 23 Table 11.2-25 -2 Sheets 23 Table 11.2-26 -2 Sheets 23 Table 11.3-1 -2 Sheets 22 Table 11.3-2 23 Table 11.3-3 -2 Sheets 23 Table 11.3-4 23 Table 11.3-5 23 Table 11.3-6 23 Table 11.3-7 23 Table 11.3-8 23 Table 11.3-9 23 Table 11.3-10 23 Table 11.3-11 23 Table 11.3-12 23 Table 11.3-13 -2 Sheets 23 Table 11.3-14 -2 Sheets 23 Table 11.3-15 23 Table 11.3-16 23 Table 11.3-17 23 Table 11.3-18 23 Table 11.3-19 23 Table 11.3-20 23 Table 11.3-21 23 Table 11.3-22 23 Table 11.3-23 23 Table 11.3-24 23 Table 11.3-25 23 Table 11.3-26 23 Table 11.3-27 23 Table 11.3-28 23 Table 11.3-29 23 Table 11.3-30 23 Table 11.3-31 23 Table 11.3-32 23 Table 11.3-33 23 Table 11.3-34 23 Table 11.3-35 23 Table 11.3-36 23 Table 11.3-37 23 Table 11.3-38 23 Table 11.3-39 23 Table 11.3-40 23 Table 11.3-41 23 Table 11.3-42 23 Table 11.3-43 23 Table 11.3-44 23 Table 11.4-1 -6 Sheets 23 Table 11.4-3 11 Table 11.5-1 23 Table 11.5-2 -2 Sheets 23 Table 11.5-4 23 Table 11.5-5 19 Table 11.6-4 -5 Sheets 23 Table 11.6-11 -2 Sheets 12 Table 11.6-13 11 Table 11.6-14 11 Figure 11.1-1 23 Figure 11.2-2 23 Figure 11.2-3 23 Figure 11.2-4 11 Figure 11.2-5 11 Figure 11.2-6 23 Figure 11.2-7 23 Figure 11.2-8 23 Figure 11.2-9 11 Figure 11.3-4 22 Figure 11.4-1 -2 Sheets 23 DCPP UNITS 1 & 2 FSAR UPDATE LIST OF CURRENT PAGES Page No. Rev. Page No. Rev. Page No. Rev.
9 Revision 23 December 2016 Figure 11.5-1 11 Figure 11.5-3 20 Figure 11.5-4 16 Figure 11.5-6 23 Figure 11.5-7 11 Figure 11.5-8 11 Figure 11.5-9 11 Figure 11.5-10 11 Figure 11.5-11 11 Figure 11.5-12 11
CHAPTER 12
i thru viii 23 12.1-1 thru 12.1-16 23 12.2-1 thru 12.2-12 23 12.3-1 thru 12.3-6 23 Table 12.0-1 23 Table 12.1-1 11 Table 12.1-2 20 Table 12.1-3 23 Table 12.1-4 23 Table 12.1-5 23 Table 12.1-6 23 Table 12.1-7 23 Table 12.1-8 23 Table 12.1-9 23 Table 12.1-10 23 Table 12.1-11 -2 Sheets 23 Table 12.1-12 23 Table 12.1-13 23 Table 12.1-14 23 Table 12.1-15 -2 Sheets 23 Table 12.2-1 23 Table 12.2-2 23 Table 12.2-3 23 Table 12.2-4 23 Table 12.2-5 23 Table 12.2-6 23 Table 12.2-7 23 Table 12.2-8 23 Table 12.2-9 23 Table 12.2-10 23 Table 12.2-11 23 Table 12.2-12 23 Table 12.2-13 23 Table 12.2-14 23 Table 12.2-15 23 Table 12.2-17 23 Table 12.2-18 -3 Sheets 23 Table 12.3-1 -3 Sheets 23 Table 12.3-2 23 Table 12.3-3 23 Figure 12.1-1 11 Figure 12.1-2 11 Figure 12.1-3 11 Figure 12.1-4 11 Figure 12.1-5 11 Figure 12.1-6 11 Figure 12.1-7 11 Figure 12.1-8 11 Figure 12.1-9 11 Figure 12.1-10 11 Figure 12.1-11 12 Figure 12.1-12 11
CHAPTER 13
i thru vi 23 13.1-1 thru 13.1-8 23 13.2-1 thru 13.2-7 23 13.3-1 23
13.4-1 23 13.5-1 thru 13.5-8 23
13.6-1 11 13.7-1 thru 13.7-2 23 Table 13.2-1 -5 Sheets 23 Table 13.2-2 -2 Sheets 23 Figure 13.1-5 23 Figure 13.2-1 11
CHAPTER 14
i thru iv 23 14.1-1 thru 14.1-11 23 14.2-1 thru 14.2-6 23
14.3-1 23 Table 14.1-1 -8 Sheets 23 Table 14.1-2 -6 Sheets 23 Figure 14.1-1 -5 Sheets 23
CHAPTER 15
i thru xliii 23 15-1 thru 15-2 22 15.1-1 thru 15.1-17 23 15.2-1 thru 15.2-61 23 15.3-1 thru 15.3-15 23 15.4-1 thru 15.4-76 23 15.5-1 thru 15.5-84 22 Table 15.0-1 -9 Sheets 22 Table 15.1-1 22 Table 15.1-2 23 Table 15.1-4 -4 Sheets 23 Table 15.2-1 -9 Sheets 23 Table 15.3-1 21 Table 15.3-2 19 Table 15.3-3 23 Table 15.4.1-1A 21 Table 15.4.1-1B 18 Table 15.4.1-2A 21 Table 15.4.1-2B 18 Table 15.4.1-3A -4 Shts 21 Table 15.4.1-3B -3 Shts 21 Table 15.4.1-4A 21 Table 15.4.1-4B 18 Table 15.4.1-5A -2 Shts 18 Table 15.4.1-5B 18 Table 15.4.1-7A -3 Shts 22 Table 15.4.1-7B -2 Shts 22 Table 15.4.8 -5 Sheets 23 Table 15.4-10 23 Table 15.4-11 15 Table 15.4-12 19 Table 15.4-13A 20 Table 15.4-13B 20 Table 15.4-14 21 Table 15.5-1 22 Table 15.5-2 22 Table 15.5-3 23 Table 15.5-4 23 Table 15.5-5 11 Table 15.5-6 11 Table 15.5-7 11 Table 15.5-8 11 Table 15.5-9 22 Table 15.5-10 22 Table 15.5-11 22 Table 15.5-12 22 Table 15.5-13 11 Table 15.5-14 11 Table 15.5-15 11 Table 15.5-17 11 Table 15.5-19 11 Table 15.5-21 11 Table 15.5-23 22 Table 15.5-24 -5 Sheets 22 Table 15.5-26 11 Table 15.5-27 -2 Sheets 22 Table 15.5-28 -2 Sheets 22 Table 15.5-29 11 Table 15.5-30 11 Table 15.5-31 -2 Sheets 22 Table 15.5-32 -3 Sheets 22 Table 15.5-33 22 Table 15.5-34 22 Table 15.5-40 22 Table 15.5-41 -2 Sheets 22 Table 15.5-42 22 Table 15.5-44 22 DCPP UNITS 1 & 2 FSAR UPDATE LIST OF CURRENT PAGES Page No. Rev. Page No. Rev. Page No. Rev.
10 Revision 23 December 2016 Table 15.5-45 -2 Sheets 22 Table 15.5-47 18 Table 15.5-48 -2 Sheets 22 Table 15.5-49 22 Table 15.5-50 22 Table 15.5-51 -2 Sheets 22 Table 15.5-52 22 Table 15.5-53 22 Table 15.5-56 22 Table 15.5-57 22 Table 15.5-63 22 Table 15.5-64 -2 Sheets 22 Table 15.5-65 19 Table 15.5-66 19 Table 15.5-67 16 Table 15.5-68 22 Table 15.5-69 22 Table 15.5-70 16 Table 15.5-71 22 Table 15.5-72 16 Table 15.5-74 19 Table 15.5-75 22 Table 15.5-76 22 Figure 15.1-1 14 Figure 15.1-2 11 Figure 15.1-3 11 Figure 15.1-4 11 Figure 15.1-5 11 Figure 15.1-6 22 Figure 15.1-7 22 Figure 15.1-8 11 Figure 15.2.1-1 11 Figure 15.2.1-2 22 Figure 15.2.1-3 11 Figure 15.2.2-1 11 Figure 15.2.2-2 11 Figure 15.2.2-3 11 Figure 15.2.2-4 11 Figure 15.2.2-5 11 Figure 15.2.2-6 11 Figure 15.2.2-7 11 Figure 15.2.3-1 11 Figure 15.2.3-2 11 Figure 15.2.4-1 11 Figure 15.2.5-1 23 Figure 15.2.5-2 23 Figure 15.2.5-3 23 Figure 15.2.5-4 23 Figure 15.2.5-5 23 Figure 15.2.6-1 11 Figure 15.2.6-2 11 Figure 15.2.6-3 11 Figure 15.2.6-4 11 Figure 15.2.6-5 11 Figure 15.2.7-1 11 Figure 15.2.7-2 11 Figure 15.2.7-3 11 Figure 15.2.7-4 11 Figure 15.2.7-9 11 Figure 15.2.7-10 22 Figure 15.2.7-11 22 Figure 15.2.7-12 11 Figure 15.2.8-1 19 Figure 15.2.8-2 19 Figure 15.2.8-3 19 Figure 15.2.9-1 22 Figure 15.2.9-2 22 Figure 15.2.9-3 22 Figure 15.2.10-1 23 Figure 15.2.10-2 23 Figure 15.2.10-3 23 Figure 15.2.12-1 22 Figure 15.2.12-2 22 Figure 15.2.12-3 22 Figure 15.2.12-4 22 Figure 15.2.12-5 22 Figure 15.2.12-6 22 Figure 15.2.12-7 22 Figure 15.2.12-8 22 Figure 15.2.13-1 22 Figure 15.2.13-2 22 Figure 15.2.15-1 16 Figure 15.2.15-2 16 Figure 15.2.15-3 18 Figure 15.2.15-4 18 Figure 15.2.15-5 18 Figure 15.3-1 13 Figure 15.3-2 -2 Sheets 21 Figure 15.3-3 -2 Sheets 21 Figure 15.3-4 -2 Sheets 21 Figure 15.3-8 13 Figure 15.3-9 -2 Sheets 21 Figure 15.3-11 -2 Sheets 21 Figure 15.3-13 -2 Sheets 21 Figure 15.3-15 21 Figure 15.3-16 21 Figure 15.3-17 21 Figure 15.3-18 21 Figure 15.3-19 21 Figure 15.3-33 -2 Sheets 21 Figure 15.3-34 -2 Sheets 21 Figure 15.3-35 -2 Sheets 21 Figure 15.3-36 -2 Sheets 21 Figure 15.3-37 -2 Sheets 21 Figure 15.3-38 -2 Sheets 21 Figure 15.3-39 -2 Sheets 21 Figure 15.3-40 21 Figure 15.3-41 21 Figure 15.3.4-1 23 Figure 15.3.4-2 23 Figure 15.3.4-3 23 Figure 15.3.4-4 23 Figure 15.4.1-1A 18 Figure 15.4.1-1B 18 Figure 15.4.1-2A 18 Figure 15.4.1-2B 18 Figure 15.4.1-3A 18 Figure 15.4.1-3B 18 Figure 15.4.1-4A 18 Figure 15.4.1-4B 18 Figure 15.4.1-5A 18 Figure 15.4.1-5B 18 Figure 15.4.1-6A 18 Figure 15.4.1-6B 18 Figure 15.4.1-7A 18 Figure 15.4.1-7B 18 Figure 15.4.1-8A 18 Figure 15.4.1-8B 18 Figure 15.4.1-9A 18 Figure 15.4.1-9B 18 Figure 15.4.1-10A 18 Figure 15.4.1-10B 18 Figure 15.4.1-11A 18 Figure 15.4.1-11B 18 Figure 15.4.1-12A 18 Figure 15.4.1-12B 18 Figure 15.4.1-13A 18 Figure 15.4.1-13B 18 Figure 15.4.1-14A 18 Figure 15.4.1-14B 18 Figure 15.4.1-15A 21 Figure 15.4.1-15B 18 Figure 15.4.2-1 19 Figure 15.4.2-2 19 Figure 15.4.2-3 21 Figure 15.4.2-4 19 Figure 15.4.2-5 19 Figure 15.4.2-6 19 Figure 15.4.2-7 19 Figure 15.4.2-8 19 Figure 15.4.2-9 19 Figure 15.4.2-10 19 Figure 15.4.2-11 19 Figure 15.4.2-12 19 Figure 15.4.2-13 19 Figure 15.4.2-14 19 Figure 15.4.2-15 19 Figure 15.4.2-16 19 Figure 15.4.2-17 19 Figure 15.4.2-18 19 DCPP UNITS 1 & 2 FSAR UPDATE LIST OF CURRENT PAGES Page No. Rev. Page No. Rev.
11 Revision 23 December 2016 Figure 15.4.2-19 19 Figure 15.4.2-20 19 Figure 15.4.2-21 19 Figure 15.4.2-22 23 Figure 15.4.2-23 23 Figure 15.4.2-24 23 Figure 15.4.2-25 23 Figure 15.4.2-26 23 Figure 15.4.2-27 23 Figure 15.4.3-1A 20 Figure 15.4.3-1B 21 Figure 15.4.3-2A 20 Figure 15.4.3-2B 21 Figure 15.4.3-3A 20 Figure 15.4.3-3B 21 Figure 15.4.3-4A 20 Figure 15.4.3-4B 21 Figure 15.4.3-5B 21 Figure 15.4.3-6A 20 Figure 15.4.3-6B 21 Figure 15.4.3-7A 20 Figure 15.4.3-7B 21 Figure 15.4.3-8A 20 Figure 15.4.3-8B 21 Figure 15.4.3-9 21 Figure 15.4.3-10 21 Figure 15.4.3-11 21 Figure 15.4.4-1 23 Figure 15.4.4-2 23 Figure 15.4.4-3 23 Figure 15.4.4-4 23 Figure 15.4.4-5 23 Figure 15.4.6-1 11 Figure 15.4.6-2 11 Figure 15.4.6-3 11 Figure 15.4.6-4 11 Figure 15.5-1 11 Figure 15.5-2 11 Figure 15.5-3 11 Figure 15.5-4 11 Figure 15.5-5 11 Figure 15.5-6 22 Figure 15.5-7 22 Figure 15.5-8 22 Figure 15.5-9 11 Figure 15.5-10 11 Figure 15.5-11 11 Figure 15.5-12 11 Figure 15.5-14 11 Figure 15.5-15 11 Figure 15.5-16 22
CHAPTER 16 i thru ii 23
16.1-1 23 Table 16.1-1 -3 Sheets 16
CHAPTER 17
i thru iv 23 17.1-1 thru 17.1-11 23 17.2-1 thru 17.2-9 23 17.3-1 thru 17.3-3 23
17.4-1 23 17.5-1 thru 17.5-3 23
17.6-1 23 17.7-1 thru 17.7-2 23
17.8-1 11
17.9-1 13 17.10-1 thru 17.10-2 23
17.11-1 23
17.12-1 23
17.13-1 11
17.14-1 11
17.15-1 22
17.16-1 23 17.17-1 thru 17.17-5 23 17.18-1 thru 17.18-4 23 Table 17.1-1 -12 Sheets 23 Figure 17.1-1 23 Figure 17.1-2 23 DCPP UNITS 1 &
2 FSAR UPDATE i Revision 23 December 2016 Chapter 1 INTRODUCTION AND GENERAL DES CRIPTION OF PLANT CONTENTS Section Title
Page
1.1 INTRODUCTION
1.1-1
1.2 GENERAL PLANT DESCRIPTION 1.2-1
1.2.1 PRINCIPAL SITE CHARACTERISTICS 1.2-1 1.2.1.1 Location (Historical) 1.2-1 1.2.1.2 Topography 1.2-1 1.2.1.3 Meteorology (Historical) 1.2-1 1.2.1.4 Hydrology 1.2-2 1.2.1.5 Geology 1.2-2 1.2.1.6 Seismology 1.2-2 1.2.1.7 Oceanography 1.2-3
1.2.2 FACILITY DESCRIPTION 1.2-3 1.2.2.1 Design Criteria 1.2-3 1.2.2.2 Nuclear Steam Supply System 1.2-4 1.2.2.3 Engineered Safety Features 1.2-5 1.2.2.4 Instrumentation and Control 1.2-6 1.2.2.5 Electrical Systems 1.2-6 1.2.2.6 Power Conversion System 1.2-7 1.2.2.7 Fuel Handling and Storage 1.2-7 1.2.2.8 Auxiliary Systems 1.2-7 1.2.2.9 Radioactive Wastes 1.2-8 1.2.2.10 Shared Facilities and Equipment 1.2-8
1.
2.3 REFERENCES
1.2-10
1.2.4 REFERENCE DRAWINGS 1.2-10
1.3 COMPARISON TABLES (Historical) 1.3-1
1.3.1 COMPARISON WITH SIMILAR FACILITY DESIGNS 1.3-1 (Historical) 1.3.2 COMPARISON OF FINAL AND PRELIMINARY DESIGNS 1.3-1 (Historical)
DCPP UNITS 1 &
2 FSAR UPDATE Chapter 1 CONTENTS (Continued)
Section Title Page ii Revision 23 December 2016 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 1.4-1 (Historical) 1.4.1 CONSULTANTS (Historical) 1.4-1 1.4.2 NUCLEAR STEAM SUPPLY SYSTEM SUPPLIER 1.4-1 (Historical)
1.4.3 OTHER EQUIPMENT SUPPLIERS (Historical) 1.4-2 1.4.4 CONSTRUCTION AND INSTALLATION CONTRACTORS 1.4-3 (Historical)
1.5 REQUIREMENTS FOR FURT HER TECHNICAL INFORMATION (Historical) 1.5-1 1.6 MATERIAL INCORPORATED BY REFERENCE 1.6-1 1.6.1 WESTINGHOUSE TECHNICAL REPORTS 1.6-1 1.6.2 MISCELLANEOUS TECHNICAL REPORTS 1.6-8 1.6.3 DRAWINGS INCORPORATED BY REFERENCE 1.6-12
DCPP UNITS 1 &
2 FSAR UPDATE Chapter 1 TABLES Table Title
iii Revision 23 December 2016 1.3-1 Design Comparison of Diablo Canyon Power Plant Units 1 & 2, Zion Station, and Trojan Nuclear Plant (Historical) 1.3-2 Major Design Changes Since the PSAR (Historical)
1.4-1 Principal Consultants and Contract Description (Historical)
1.4-2 Suppliers of Important Equi pment and Materials Other than Nuclear Steam Supply System (Historical)
1.4-3 Construction and Installation Contractors (Historical)
1.5-1 Research and Development Programs (Historical) 1.6-1 Controlled Engineering Drawings/FSAR Update Figures Cross Reference
DCPP UNITS 1 &
2 FSAR UPDATE Chapter 1 FIGURES Figure Title
iv Revision 23 December 2016 1.2-1 Plot Plan 1.2-2 Plant Layout 1.2-3 (a) Area Location Plan
1.2-4 (a) Auxiliary, Containment, and Fuel Handling Buildings (Units 1 & 2), Plan at Elevation 140 ft
1.2-5 (a) Auxiliary, Containment, and Fuel Handling Buildings (Units 1 & 2), Plan at Elevation 115 ft
1.2-6 (a) Auxiliary, Containment, and Fuel Handling Buildings (Units 1 & 2), Plan at Elevations 91 and 100 ft
1.2-7 (a) Auxiliary and Containment Buildi ngs (Units 1 & 2), Plan at Elevation 85 ft
1.2-8 (a) Auxiliary and Containment Buildi ngs (Units 1 & 2), Plan at Elevation 73 ft
1.2-9 (a) Auxiliary and Containment Buildi ngs (Unit 1 & 2), Plan at Elevations 60 and 64 ft
1.2-10 (a) Containment Building (Unit 2), Plan at Elevations 115 and 140 ft
1.2-11 (a) Containment & Fuel Handling Bui ldings (Unit 2), Plan at Elevations 85, 91, and 100 ft
1.2-12 (a) Containment Building (Unit 2), Plan at Elevations 60, 64, and 73 ft
1.2-13 (a) Turbine Building (Unit 1), Plan at Elevation 140 ft
1.2-14 (a) Turbine Building (Unit 1), Plan at Elevation 119 ft
1.2-15 (a) Turbine Building (Unit 1), Plan at Elevation 104 ft
1.2-16 (a) Turbine Building (Unit 1), Plan at Elevation 85 ft 1.2-17 (a) Turbine Building (Unit 2), Plan at Elevation 140 ft
DCPP UNITS 1 &
2 FSAR UPDATE Chapter 1 FIGURES Figure Title
v Revision 23 December 2016 1.2-18 (a) Turbine Building (Unit 2), Plan at Elevation 119 ft 1.2-19 (a) Turbine Building (Unit 2), Plan at Elevation 104 ft 1.2-20 (a) Turbine Building (Unit 2), Plan at Elevation 85 ft
1.2-21 (a) Auxiliary Building (Units 1 & 2), Section A-A
1.2-22 (a) Auxiliary and Containment Buildings (Unit 1 & 2), Section B-B 1.2-23 (a) Auxiliary and Fuel Handling Buildings (Unit 1 & 2), Section C-C 1.2-24 (a) Containment, Turbine, and Fuel Hand ling Buildings (Unit 1)
Section D-D
1.2-25 (a) Auxiliary, Turbine, and Fuel Han dling Buildings (Unit 1), Section E-E
1.2-26 (a) Auxiliary, Fuel Handling, and Turbine Buildings (Units 1 & 2), Section F-F
1.2-27 (a) Turbine Building (Unit 1), Section G-G
1.2-28 (a) Containment Building (Unit 2), Section A-A
1.2-29 (a) Vent & Fuel Handling Buildings (Unit 2), Section B-B
1.2-30 (a) Turbine, Containment, & Fuel Handling Buildings (Unit 2),
Section C-C
1.2-31 (a) Turbine Building (Unit 2), Sections D-D and E-E
1.2-32 (a) Turbine Building (Unit 2), Section F-F
NOTE:
(a) This figure corresponds to a controlled engineering drawing that is incorporated by reference into the FSAR Update. See Table 1.6-1 for the correlation between the
FSAR Update figure number and the corresp onding controlled engineering drawing number.
DCPP UNITS 1 &
2 FSAR UPDATE 1.1-1 Revision 23 December 2016 CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT
1.1 INTRODUCTION
The Updated Final Safety Analysis Report (U FSAR) for the Diablo Canyon Power Plant (DCPP) is submitted in accordance with the requirements of 10 CFR 50.71(e) and
contains all the changes necessary to reflect information and analyses submitted to the
U.S. Nuclear Regulatory Commission (NRC) by Pacific Gas and Electric Company (PG&E) or prepared by PG&E pursuant to NRC requirements since the submittal of the
original FSAR.
HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED The original FSAR was submitted in support of applications for permits to operate two substantially identical nuclear power units (Unit 1 and Unit 2) at the DCPP site. The
DCPP site is located on the central Cal ifornia coast in San Luis Obispo County, approximately 12 miles west southwest of the city of San Luis Obispo.
The Construction Permit for Unit 1 (CPPR-39) was issued April 23, 1968, in response to
PG&E's application dated January 16, 1967 (USAEC, Docket No. 50-275). The
Construction Permit for Unit 2 (CPPR-69) was issued on December 9, 1970; the
application was made on June 28, 1968 (USAEC, Docket No. 50-323).
Westinghouse Electric Corporation and PG&E jointly participated in the design and
construction of each unit. The plant is operated by PG&E. Each unit employs a
pressurized water reactor (PWR) nuclear steam supply system (NSSS) furnished by
Westinghouse Electric Corporation and similar in design concept to several projects
licensed by the NRC.
Certain components of the auxiliary systems are shared by the two units, but in no case
does such sharing compromise or impair the safe and continued operation of either unit.
Those systems and components that are shared are identified and the effects of the
sharing are discussed in the chapters in which they are described (refer to Section 1.2.2.10).
The NSSS for each unit is contained within a steel-lined reinforced concrete structure
that is capable of withstanding the pressure that might be developed as a result of the
most severe postulated loss-of-coolant accident (LOCA).
HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED The containment structure was designed by PG&E to meet the requirements specified
by Westinghouse Electric Corporation.
DCPP UNITS 1 &
2 FSAR UPDATE 1.1-2 Revision 23 December 2016 While the reactors, structures, and all auxiliary equipment are substantially identical for the two units, there is a difference in the reactor internal flow path that results in a lower
coolant flow rate for Unit 1.
HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Consequently, the original license application reactor ratings were 3,338 MWt for Unit 1 and 3,411 MWt for Unit 2. The corresponding net electrical outputs were approximately 1,084 MWe and 1,106 MWe, respectively.
During the design phase, the expected ultimate output of the Unit 1 reactor was
3,488 MWt; the expected ultimate output of the Unit 2 reactor was 3,568 MWt. The corresponding NSSS outputs were 3,500 MWt and 3,580 MWt. (The difference of
12 MWt is due to the net contribution of heat to the reactor coolant system (RCS) from nonreactor sources, primarily pump heat.) The corresponding estimated ultimate net
electrical outputs were 1,131 MWe for Unit 1 and 1,156 MWe for Unit 2.
The NRC issued a low power-operating license for Unit 1 on September 22, 1981.
PG&E voluntarily postponed fuel loading due to the discovery of design errors in the annulus region of the containment structure. Subsequently, the NRC suspended
portions of the license on November 19, 1981, pending completion of an Independent Design Verification Program.
After completion of redesign and construction activities in November 1983, the NRC
reinstated the fuel load portion of the Unit 1 low power-operating license. On
April 19, 1984, the NRC fully reinstated the l ow power-operating license, which included low power testing. The Unit 1 full power-operating license was issued on November 2, 1984. Commercial operation for Unit 1 began on May 7, 1985, with a
license expiration date of April 23, 2008.
The NRC issued a low power-operating license for Unit 2 on April 26, 1985. Unit 2 fuel
loading was completed on May 15, 1985.
A full power-operating license for Unit 2 was issued on August 26, 1985. Unit 2 commerc ial operation began on March 13, 1986, with a license expiration date of December 9, 2010.
In March 1996, the NRC approved license amendments extending the operating license
for Unit 1 until September 22, 2021, and for Unit 2 until April 26, 2025.
In July 2006, the NRC approved license amendments extending the operating license for Unit 1 until November 2, 2024, and for Unit 2 until August 26, 2025.
In October 2000, the NRC approved a licen se amendment (LA) 143 to increase the Unit 1 rated reactor thermal power from the original value of 3,338 MWt to 3,411 MWt to increase production and be consistent with Unit 2.
LA 143 also documented the evaluation performed to revise the net contribution of heat to the RCS from nonreactor DCPP UNITS 1 &
2 FSAR UPDATE 1.1-3 Revision 23 December 2016 sources (primarily pump heat) to a nominal value of 14 MWt and established a NSSS power outlet of 3,425 MWt for both Unit 1 and Unit 2.
DCPP UNITS 1 &
2 FSAR UPDATE 1.2-1 Revision 23 December 2016 1.2 GENERAL PLANT DESCRIPTION 1.2.1 PRINCIPAL SITE CHARACTERISTICS HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED 1.2.1.1 Location
The DCPP site consists of approximately 750 acres located in San Luis Obispo County, California, adjacent to the Pacific Ocean and roughly equidistant from San Francisco and Los Angeles. The site location, the site boundary, and the location of principal structures are shown in Figure 1.2-1. The minimum distance from either reactor to the
nearest site boundary on land is one-half mile, the minimum exclusion distance. The low population zone (LPZ), as defined in 10 CFR Part 100, is the area immediately surrounding the exclusion area. For DCPP, the LPZ is an area encompassed by a
radius of 6 miles. This zone contains reside nts for whom there is reasonable probability that appropriate protective measures, as described in the DCPP Emergency Plan (Reference 1) can be taken in the event of a serious accident. The population center
distance, as defined by 10 CFR Part 100, is approximately 10 miles, the distance to the nearest boundary of the city of San Luis Obispo.
1.2.1.2 Topography The plant site occupies a coastal terrace that ranges in elevation from 60 to 150 feet
above sea level and is approximately 1000 feet wide. Plant grade is at elevation
85 feet. The seaward edge of the terrace is a near-vertical cliff. Back from the terrace and extending for several miles inland are the rugged Irish Hills, an area of steep, brush-covered hillsides and deep canyons that are part of the San Luis Mountains and attain an elevation of 1500 feet within about a mile of the site. Access to the site is by a
private road from Avila Beach, a distance of nearly 8 miles.
HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED 1.2.1.3 Meteorology
The climate of the site area is typical of that along the central California coast. In the
dry season, mainly May through September, the Pacific Anticyclone stays off the
California coast and prevents Pacific storms from moving eastward across the state. In
the winter or wet season, November through March, the Pacific Anticyclone moves
southward, weakening in intensity, and allows Pacific storms to enter the state. More
than 80 percent of the average annual rainfall of 16 inches occurs during this 5-month
period. April and October are considered transitional months. The average annual
temperature of the site area is about 55°F, which reflects the strong maritime influence.
Most stations along the coast show a 5 to 10°F mean temperature difference between
the coldest winter month and the warmest summ er month. Extreme temperatures may DCPP UNITS 1 &
2 FSAR UPDATE 1.2-2 Revision 23 December 2016 range from 104°F in the summer to as low as 24°F in the winter. However, the recurrence interval of days having these extremes is in the order of 5 to 10 years.
Maximum summer temperatures of 85°F and mi nimum winter temperatures of 35°F are exceeded only 1 percent of the time at both Morro Bay and Pismo Beach. Additional
site temperature data are presented in Section 2.3. The onsite meteorological measurements program was initiated in July 1967. Data collected are presented in Section 2.3 and are used to establish atmospheric diffusion characteristics of the site.
Severe weather conditions, such as tornadoes and hurricanes, have not been recorded
in this area. Thunderstorms are also a rare phenomenon with the average occurrence
of lightning being less than 3 days per year.
1.2.1.4 Hydrology Hydrological considerations at the plant site are limited to possible effects of plant
operations on domestic water supplies and to the possibility of flooding. A survey of
domestic water supplies in the environs shows that operation of the plant will not
jeopardize any existing or planned facility. The topography of the site and the limited
rainfall preclude any possibility of flooding.
1.2.1.5 Geology A comprehensive geological investigation has demonstrated that the site is geologically suitable for a nuclear power plant. Foundations are on firm bedrock fully capable of
carrying the loads. Movement along the few small breaks in the vicinity of the plant has
not occurred for at least 100,000 years and may well have taken place millions of years
ago. The site was investigated in detail for faulting and other possibly detrimental geologic conditions. Results of faulting inv estigations are discussed in Section 2.5.4.7 and are based on site geology data presented in Section 2.5.2.2. Landslides do not threaten the plant.
HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED 1.2.1.6 Seismology Seismological investigations were undertaken to determine the potential for earthquakes in the site area, to form a basis of the establishment of seismic design criteria, and to evaluate the adequacy of seismic design margins for the plant (refer to Section 2.5). Records indicate that seismic activity within 20 miles of Diablo Canyon has been very low compared to other parts of California. Until PG&Es seismological investigation of the Hosgri fault zone located approximately 3 miles offshore, the
seismically significant fault system nearest th e site was considered to be the Nacimiento Fault located about 20 miles away as discussed in Section 2.5.3.9. The largest earthquake known to have been associated with this fault system occurred at an
epicentral distance to the site of about 44 miles.
It is listed with a Richter magnitude 6.
At its closest point, the San Andreas Fault passes s ome 48 miles from the site.
DCPP UNITS 1 &
2 FSAR UPDATE 1.2-3 Revision 23 December 2016 PG&E's reevaluation of the plant's capability to withstand a Richter magnitude 7.5 "Hosgri" Earthquake is discussed in Section 3.7.
1.2.1.7 Oceanography Condenser cooling water for the plant is pumped from the Pacific Ocean and returned to
the ocean at Diablo Cove through an outfall at the water's edge. Controlled releases of
low-level liquid radioactive wastes are discussed in Section 11.2. The Pacific Ocean in the area of the site is turbulent and has a great capacity for dilution of wastes and
diffusion of heated cooling water. Investigatio ns of the occurrence and maximum size of tsunamis (seismic sea waves) coincident with high tide and with short period storm
waves are discussed in Section 2.4.7. These studies showed that extreme water elevation within the intake basin without a breakwater would be 44.32 feet above mean
lower low water. The intake structure houses the safety-related auxiliary cooling water
systems, which are protected against tsunami and wave splash with watertight
compartments. This is discussed in Section 2.4.6.7.
1.2.2 FACILITY DESCRIPTION The plant incorporates two substantially ide ntical PWR nuclear power units, each consisting of an NSSS, turbine-generator, aux iliary equipment, controls, and instrumentation. The general arrangement of the plant and the site is shown in
Figure 1.2-1. Principal structures, shown in Figure 1.2-2, include the containment
structures, turbine building, and auxiliary buil ding (which includes the control room, the fuel handling areas, and the ventilation areas). Arrangement plans and sections are
shown in Figures 1.2-3 through 1.2-32. The descriptions that follow apply to both units unless otherwise specified.
1.2.2.1 Design Criteria The principal design criteria for the DCPP nuclear units are those fundamental
architectural and engineering design objectives established for the plant. The bases for
development and selection of the design criteria used in this plant are: (a) those that
provide protection to public health and safety, (b) those that provide for reliable and economic plant performance, and (c) those that provide an attractive external
appearance to the plant.
The essential systems and components of the plant are designed to enable the facility
to withstand, without loss of capability to protect the public, the forces resulting from
normal operation plus those that might be imposed by natural phenomena. The designs
are based on the most severe of the natural phenomena recorded for the vicinity of the
site, with margin to account for uncertainties in the historical data.
The DCPP units are designed to comply with the "General Design Criteria for Nuclear
Power Plant Construction Permits," published in July 1967. A discussion of
conformance to these criteria is contained in Section 3.1. In addition, a summary DCPP UNITS 1 &
2 FSAR UPDATE 1.2-4 Revision 23 December 2016 discussion of the designs and procedures that are intended to meet the NRC General Design Criteria published as Appe ndix A to 10 CFR Part 50 in 1971 is provided in Chapter 3, Section 3.1, Appendix 3.1A.
1.2.2.2 Nuclear Steam Supply System The NSSS consists of a PWR and associated auxiliary fluid systems. The RCS consists of four parallel reactor coolant loops, each containing a steam generator and a
reactor coolant pump (RCP). A pressurizer is connected to the hot leg of one reactor coolant loop.
The reactor core is composed of an array of 193 fuel assemblies, each containing
264 fuel rods. These rods are composed of uranium dioxide pe llets enclosed in zirconium alloy tubes with welded end plugs.
All fuel rods are pressurized with helium during fabrication to reduce stress and increase fatigue life. Reactor control and
shutdown functions are performed by the rod cluster control assemblies (RCCAs). The
RCCAs are stainless steel tubes containing a silver-indium-cadmium absorber and are
positioned by drive mechanisms of the magnetic latch type. A soluble poison (boron) is introduced into the reactor coolant to compensate for long-term reactivity changes. The moderator temperature coefficient can be slightly positive at the beginning of cycle
when boron concentration is high. However, for most operating conditions, the moderator coefficient is non-positive, but the power coefficient is negative at all times.
The reactor vessel and reactor internals contain and support the fuel and RCCAs. The
vessel is cylindrical with hemispherical heads and is clad with stainless steel.
The pressurizer is a vertical cylindrical pressure vessel with hemispherical heads and is
equipped with electrical heaters and spray nozzles for system pressure control.
The steam generators are vertical U-tube type heat exchangers with Inconel tubes.
Reactor coolant flows inside the tubes; steam is generated in the shell and flows
through the main steam lines to the turbine. When operating at 100 percent power, integral moisture separating equipment reduces moisture content of the steam at the
<0.25 percent. The RCPs are vertical, single-stage, centrifugal units equipped with controlled leakage shaft seals.
Auxiliary systems are provided to charge the RCS and add makeup water, to purify reactor coolant water, to provide chemicals for corrosion inhibition and reactor control, to cool system components, to remove residual heat when the reactor is shut down, to
cool the spent fuel storage pool, to sample reactor coolant water, to provide for
emergency safety injection, and to vent and drain the RCS. Refer to Chapters 4 and 5 for additional discussion of the reactor and RCS, respectively.
DCPP UNITS 1 &
2 FSAR UPDATE 1.2-5 Revision 23 December 2016 1.2.2.3 Engineered Safety Features The engineered safety features (ESFs) provided for the DCPP have sufficient capacity
and redundancy to protect the health and safety of the public by keeping exposure below the limits set forth in 10 CFR Part 100 for any of the postulated malfunctions or accidents, including the most severe LOCA (refer to Chapter 15 for additional discussion). .
The ESFs provided in the DCPP are:
(1) A containment system that consists primarily of a steel-lined, reinforced concrete containment structure designed to prevent significant release to
the environs of radioactive materials that could result from accidents
inside the containment (refer to Sections 6.2.1 and 6.2.4).
(2) An emergency core cooling system (ECCS) that provides water to cool the core in the event of an accidental loss of primary reactor coolant water.
The ECCS also supplies dissolved boron into the cooling water to provide shutdown margin (refer to Section 6.3).
(3) A containment spray system (CSS) to help limit the peak temperature and pressure in the containment in the event of a LOCA or main steam line
break (MSLB) (refer to Section 6.2.2). The CSS, in conjunction with the
spray additive system (SAS), also helps to limit the offsite radiation levels
following the postulated LOCA by removing airborne iodine from the
containment atmosphere during the injection phase (refer to Section 6.2.2 and 6.2.3).
(4) A containment fan cooler system (CFCS) that functions in conjunction with the CSS to limit the temperature and pressure in the containment structure in the event of a LOCA or MSLB (refer to Section 6.2.2). The CFCS also
provides mixing of the sprayed and unsprayed regions of the containment atmosphere to improve airborne fission product removal (refer to Section
6.2.3). The CFCS function of mixing the containment atmosphere for
hydrogen control is discussed below.
(5) A SAS that functions by adding sodium hydroxide, an effective iodine scrubbing solution, to the CSS water, to reduce the content of iodine and
other fission products in the containment atmosphere and prevent the re-
evolution of the iodine in the recirculated core cooling solution following a
LOCA (refer to Section 6.2.3).
(6) The long term buildup of gaseous hydrogen in the containment following a LOCA is primarily controlled by ensuring a mixed containment atmosphere
and providing equipment for monitoring hydrogen concentrations. The DCPP UNITS 1 &
2 FSAR UPDATE 1.2-6 Revision 23 December 2016 CFCS is the primary means credited for containment atmosphere mixing (refer to Section 6.2.5).
(7) A fuel handling buildin g ventilation system provides a significant reduction in the amounts of volatile radioactive materials that could be released to
the atmosphere in the event of a major fuel handling accident (refer to
Section 9.4.4).
(8) An auxiliary building ventilation system (ABVS) that provides the capability for significant reduction in the amounts of volatile radioactive materials
that could be released to the atmosphere in the event of leakage from the
residual heat removal system recirculation loop following a LOCA (refer to Section 9.4.2).
(9) A control room ventilation system (CRVS) permits continuous occupancy of the control room and technical support center (TSC) under design basis
accidents by providing the capability to control infiltration of volatile
radioactive material (refer to Sections 6.4.1 and 9.4.1).
(10) An auxiliary feedwater (AFW) system supplies water to the secondary side of the steam generators for reactor decay heat removal, when the main
feedwater system is unavailable (refer to Section 6.5).
1.2.2.4 Instrumentation and Control The primary purpose of the instrumentation and control system is to provide automatic protection against unsafe and improper reactor operation during steady state and transient power operation (ANS Conditions I, II, and III) and to provide initiating signals
to mitigate the consequences of faulted conditions (ANS Condition IV). These plant
conditions are discussed in Chapter 15, Accident Analysis.
The operation of the plant is monitored and controlled by operators in the control room, which is located in the auxiliary building.
Refer to Chapter 7 for additional discussio n of the various instrumentation systems.
1.2.2.5 Electrical Systems The electrical systems generate and transmit power to PG&E's high-voltage system, distribute power to the auxiliary loads, and provide control, protection, instrumentation, and annunciator power supplies for the units.
Power is generated at 25-kV. Auxiliary loads are served at 12-kV, 4.16-kV, 480-V, 120-Vac, 125-Vdc, and 250-Vdc.
Offsite ac power (the preferred power supply) for the units' auxiliarie s is available from two 230-kV transmission circuits and three 500-kV transmission circuits.
DCPP UNITS 1 &
2 FSAR UPDATE 1.2-7 Revision 23 December 2016 Onsite ac auxiliary power is supplied by each unit's main generator (normal onsite power source) and is also available for Class 1E loads from six diesel engine-driven generators (standby power supply). Three diesel generators are dedicated to each unit.
Onsite dc power is provided by three Class 1E and two non-Class 1E 125-Vdc batteries in each unit. The two non-Class 1E batteries are connected in series to provide 250-Vdc power in each unit.
Refer to Chapter 8 for additional discussion of the various electric power systems.
1.2.2.6 Power Conversion System The turbines are each tandem-compound, four-element, 1800 rpm units, having one
high-pressure and three identical double flow low-pressure elements. Combination
moisture separator-reheaters are employed between the high- and low-pressure
elements to dry and superheat the steam. T he auxiliaries include deaerating surface condensers, steam jet air ejectors, motor-driven condensate pumps, motor-driven
condensate booster pumps, turbine-driven main feedwater pumps, six stages of
feedwater heating, and a full flow condensate demineralizer system.
The steam and power conversion system is designed to receive the heat generated by
the RCS during normal power operation, as well as following an emergency shutdown
of the turbine-generator from full load. Heat rejection under the latter condition is
accomplished by steam bypass to the condenser and pressure relief to the atmosphere.
Refer to Chapter 10 for additional discussion of the steam and power conversion system. 1.2.2.7 Fuel Handling and Storage
The reactor is refueled using equipment designed to handle spent fuel under water from
the time it leaves the reactor vessel until it is placed in a cask either for transport to the
Diablo Canyon Independent Spent Fuel Storage Installa tion or for shipment from the site. Underwater transfer of spent fuel provides an optically transparent radiation shield, as well as a reliable source of coolant for removal of decay heat. Spent fuel is stored
onsite in the spent fuel pools, which are fitted with special spent fuel storage racks to
ensure that criticality cannot be approached. The fuel handling system (FHS) also provides capability for receiving, handling, and storing new fuel assemblies. Refer to Section 9.1.4 for additional discussion.
1.2.2.8 Auxiliary Systems Auxiliary systems are supporting systems included in the facility, some of which are
required to perform certain functions during emergency or accident conditions such as supporting the ESFs. Included are the cooling water systems (refer to Section 9.2), the heating and ventilating systems (refer to Section 9.4), the fire protection system (refer to DCPP UNITS 1 &
2 FSAR UPDATE 1.2-8 Revision 23 December 2016 Section 9.5.1), the process auxiliaries (refer to Sections 9.3.2, 9.3.3, and 9.3.7), the compressed air system (refer to Sections 9.3.1 and 9.3.6), the diesel generator fuel oil system (refer to Section 9.5.4), the communication systems (refer to Section 9.5.2), and the lighting systems (refer to Section 9.5.3).
1.2.2.9 Radioactive Wastes The radioactive waste treatment systems provide all equipment necessary to collect, process, monitor, and discharge radioactive liquid, gaseous, and solid wastes that are
produced during reactor operation. Refer to Sections 11.2, 11.3, and 11.5 for additional discussion. A major portion of the waste treatment equipment is common for Unit 1 and Unit 2. This equipment is located in the shared auxiliary building (refer to Section 1.2.2.10.5).
1.2.2.10 Shared Facilities and Equipment Separate systems and equipment are provided for each unit, with few exceptions. A
brief summary of shared facilities and equipment between both units follows.
Interconnections between systems for Unit 1 and Unit 2 are shown in the system
diagrams. The system diagrams are contained in the UFSAR chapters referenced in the following paragraphs.
1.2.2.10.1 Site Facilities The two units share a common auxiliary building (refer to Section 3.8.2.3). The turbine building is common to both units (refer to Section 3.8.3). The machine shop, access control area, warehouse area, telecommunications systems (refer to Figure 9.5-1), and administrative offices are common.
The two units also share a common raw water storage reservoir (refer to Section 6.5.3.3), fire pumps (refer to Section 9.5.1), fire water storage tank (refer to Section 9.5.1), diesel fuel oil storage tanks and trans fer pumps (refer to Section 9.5.4.3.3), auxiliary boiler (refer to Section 9.3.7.1.3.3), makeup water system (refer to Section 9.2.3.3.3), plant air system (refer to Sections 9.3.1.3.3 and 9.3.6.3.3), and lubricating oil storage system.
Refer to Section 9.1.4.3.2 for a discussion of sharing of the FHS. Refer to Section 9.3.3.3.2 for a discussion of sharing of the equipment and floor drainage system.
1.2.2.10.2 Electrical Systems
The 230-kV line from the 230-kV switchyard serves the standby startup transformers for both Unit 1 and Unit 2. These are normally arranged on the low voltage sides to serve a single unit; however, the 12-kV buses for Unit 1 and Unit 2 are connected by an open circuit breaker (refer to Sections 8.2.3.1 and 8.3.1.1.2.3.2, respectively).
DCPP UNITS 1 &
2 FSAR UPDATE 1.2-9 Revision 23 December 2016 The plant has six diesel generator sets for emergency power. Refer to Section 8.3.1.1.6.3.3 for a discussion of sharing of diesel generator support systems.
Refer to Section 8.3.1.1.4.3.3 for a discussion of sharing of the 480-V system. Refer to Section 8.3.1.1.5.3.3 for a discussion of sharing of the 120-Vac system. Refer to Section 8.3.2.3.3 for a discussion of sharing of the 125-Vdc system.
1.2.2.10.3 Control Room The plant is provided with a central control room located in the auxiliary building which
is common to Unit 1 and Unit 2. Physical separation of control panels prevents interaction of the Unit 1 and Unit 2 control systems. Refer to Section 6.4.1.3.3 for a discussion of the common CRVS and common control room pressurization system, and Section 9.4.1.3.3 for a discussion of the com mon control room heating, ventilation and air-conditioning (HVAC) system.
Refer to Section 5.1.8.3 for a discussion of sharing of the RCP vibration monitoring system.
1.2.2.10.4 Chemical and Volume Control System Several components of the chemical and volume control system are shared, as detailed
in Chapter 9 (refer to Section 9.3.4.3.3).
1.2.2.10.5 Radioactive Waste Treatment Systems
The major portion of the waste treatment equipment is shared by Unit 1 and Unit 2.
This equipment is located in the shared auxili ary building and is described in Chapter 11 (refer to Sections 11.2.3.3, 11.3.3.3, and 11.5.3.2).
1.2.2.10.6 Emergency Facilities and Equipment The emergency facilities and equipment, both onsite and offsite, are discussed in the
Emergency Plan which applies to both Unit 1 and Unit 2. For a discussion of the TSC habitability and HVAC systems (refer to Sections 6.4.2.3.1, 9.4.1.3.3, and 9.4.11.3.1).
1.2.2.10.7 Other Systems Refer to Sections 9.2.6.3.3 and 6.5.3.3 for a discussion of the sharing of the condensate storage tanks.
Refer to Section 9.2.2.3.3 for a discussion of the sharing of the component cooling water system.
Refer to Section 9.2.7.3.3 for a discussion of the sharing of the auxiliary saltwater system.
DCPP UNITS 1 &
2 FSAR UPDATE 1.2-10 Revision 23 December 2016 Refer to Section 9.2.1.3.1 for a discussion of the sharing of the service cooling water system. Refer to Section 9.2.5.3.2 for a discussion of the sharing of the ultimate heat sink system.
Refer to Section 9.4.23.3 for a discussion of the sharing of the ABVS.
Refer to Section 6.5.3.3 for a discussion of the sharing of the AFW system.
Refer to Section 10.3.3.3 for a discussion of the sharing of the main steam system.
1.
2.3 REFERENCES
- 1. Emergency Plan, Diablo Canyon Power Plant - Units 1 and 2, Pacific Gas and Electric Company.
1.2.4 REFERENCE DRAWINGS Figures representing controlled engineering drawings a re incorporated by reference and
are identified in Table 1.6-1. The contents of the drawings are controlled by DCPP
procedures.
DCPP UNITS 1 &
2 FSAR UPDATE 1.3-1 Revision 23 December 2016 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED 1.3 COMPARISON TABLES 1.3.1 COMPARISON WITH SIMILAR FACILITY DESIGNS
Table 1.3-1 presents a comparison of the pri ncipal similarities and differences of the design of the DCPP units with those of Unit 1 at Trojan Nuclear Power Plant and Unit 1 and Unit 2 at Zion Station. This comparison is historical in nature and is valid only through March 1984.
1.3.2 COMPARISON OF FINAL AND PRELIMINARY DESIGNS
Table 1.3-2 identifies the major design chan ges made since the submittal of the DCPP Unit 2 Preliminary Safety Analysis Report. The comparison was considered to be valid
through July 1974.
DCPP UNITS 1 &
2 FSAR UPDATE 1.4-1 Revision 23 December 2016 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS PG&E is the architect engineer, constructor, operator, and owner of DCPP and, as
such, assumes full responsibility and authority for the design, construction, startup, and operation of Diablo Canyon Unit 1 and Unit 2. This section identifies the principal consultants, the nuclear steam system supplier, the suppliers of other equipment
affecting nuclear safety, and the principal contractors engaged in the construction of the units. PG&E has performed all work for the planning, design, estimating, procurement, construction, installation, inspection, testing, and associated services necessary to
provide complete plans and specifications and related services necessary to furnish a
complete, operable, and acceptable plant, e xcept for those items and functions that were furnished by those mentioned below.
1.4.1 CONSULTANTS
The consultants whose contracts exceed one hundred thousand dollars are listed in
Table 1.4-1. The list is historical in nature and is valid only through March 1986. They performed investigations and submitted reports and recommendations to PG&E on the subjects indicated in the table. Application of the material submitted is the responsibility
of PG&E.
1.4.2 NUCLEAR STEAM SUPPLY SYSTEM SUPPLIER
The NSSS was designed and furnished by the Westinghouse Electric Corporation.
Westinghouse performed the detailed engin eering design for all Westinghouse-supplied components and systems of the NSSS and procured, expedited, inspected, and delivered to PG&E all such equipment and components.
Westinghouse provided design criteria, outline and/or assembly drawings, systems flow diagrams, and other
data, as required, for PG&E to install, erect, operate, and maintain Westinghouse-supplied equipment and components. For all Westingho use-supplied nuclear auxiliary systems, Westinghouse performed systems engineering, prepared reference designs
and systems descriptions, and provided overall operating and engineering instructions.
Westinghouse further provided pertinent design criteria and data on the NSSS to enable PG&E to design the balance of plant. Westinghouse provided functional test procedures and technical assistance during construction, installation, inspections, and testing of its equipment and syste ms. A description of Westinghouse-provided technical assistance is given in Chapter 14, Initial Tests and Operations.
Westinghouse also performed the post-accident transient analysis of the plant
containment system. This analysis consisted of determining the mass and energy releases (including metal-water reaction) as a function of time for the design basis LOCA and MSLB. From the foregoing data, PG&E has determined the design pressure and temperature, containment volume cool ing requirements, etc. In general, Westinghouse has performed such transient analyses on the plant as are required for DCPP UNITS 1 &
2 FSAR UPDATE 1.4-2 Revision 23 December 2016 the Westinghouse-furnished NSSS and turbine-generator unit. Transient analyses involving non-Westinghouse-supplied systems and components are PG&E's
responsibility.
Westinghouse also supplied mat erial that is informational in nature, some of which appears in response to questions asked of Westinghouse during review meetings.
Other information and recommendations have been offered by Westinghouse from their
background experience. This type of material is not contractually binding for either
company, nor was it intended to be a commitment of final design or operation. This
material includes:
(1) The conceptual design of the dry reactor containment system. The specific designs of the reactor containment structure and associated ESFs
are developed by PG&E.
(2) The details of a recommende d waste disposal system that consists of equipment to collect, process, and dispose of radioactive liquid, gaseous, and solid wastes produced as a result of reactor operation (3) Five recommended ESFs that consist of: steel-lined concrete reactor containment vessel, the safety injection system, the containment fan
coolers, the containment spray equipment, and the air recirculation filters.
Emergency power systems to operate the ESF systems are also as
recommended by Westinghouse.
(4) The details of the recomme nded fuel handling facilities including structures, equipment, transfer, and operation (5) The details of the recommended sa mpling system and analytical facilities (6) The details of the reco mmended radiation shielding (7) The outline of a recommended health physics program and recommended supplies (8) The general criteria and preliminary design data for certain balance of plant.
Westinghouse, as a supplier to PG&E, is required to conform to the PG&E Quality
Assurance Program as described in Chapter 17, Quality Assurance.
1.4.3 OTHER EQUIPMENT SUPPLIERS Suppliers of important equipment or materials furnished to PG&E are listed in Table 1.4-2. In each case, the equipm ent was fabricated, or the material supplied qualified, to written specifications and, if PG&E Design Class I, under the Quality DCPP UNITS 1 &
2 FSAR UPDATE 1.4-3 Revision 23 December 2016 Assurance Program in effect at the time of purchase. This list of suppliers is historical in nature and is valid only through March 1986.
1.4.4 CONSTRUCTION AND INSTALLATION CONTRACTORS
The principal construction and installation contractors whose contracts exceed one
hundred thousand dollars are listed in Table 1.4-3. The list of contractors is historical in
nature and is valid only through March 1986. The contracts are agreements between
PG&E as owner-constructor and the contractors as independent contractors, with
specific provisions for inspection, testing, and quality assurance.
Each contract specification identifies any PG&E Design Class I equipment involved and requires the implementation of the supplier's Quality Assurance Program (refer to Chapter 17, Quality Assurance). In addition, PG&E maintains a staff of inspectors to
assure the quality of non-Class I equipment installation.
DCPP UNITS 1 &
2 FSAR UPDATE 1.5-1 Revision 23 December 2016 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED 1.5 REQUIREMENTS FOR FURTHE R TECHNICAL INFORMATION The design of DCPP is based on proven concepts, systems, and equi pment in order to minimize the potential for cost and schedule overruns and to enhance the rel iability of operation. As a consequence, there have been few requirements for research and development programs to confir m the adequacy of the design. Those programs identified for DCPP ha ve been satisfactorily c ompleted, as well as any other programs that have been identified as va luable to define margin s of conservatism or possible design improvements.
Table 1.5-1 is a list of those programs that have been addressed in earlier revisions of the original FSAR. This table provides a listing of the technical reports that include a d iscussion of the programs and their results. The listing is historical in nature and is valid only through November 1975.
DCPP UNITS 1 &
2 FSAR UPDATE 1.6-1 Revision 23 December 2016 1.6 MATERIAL INCORPORATED BY REFERENCE 1.6.1 WESTINGHOUSE TECHNICAL REPORTS Date Section Submitted Title Reference To AEC/NRC 1. C. J. Kubit, Safety-Related Research and Development for Westinghouse Pressurized Water Reactors, Program Summaries-Fall, 1971-Spring, 1972, WCAP-7856, April 1972.
1.5 5/9/72
- 2. F. T. Eggleston, Safety-Related Research and Development for Westinghouse PWRs, Program Summaries. Winter 77 - Summer 78, WCAP-8768, Revision 2, October 1978.
1.5, 4.2 10/78 3. R. M. Hunt, Safety-Related Research and Development for Westinghouse PWRs, Program Summaries. Fall 1970, WCAP-7614-L, November 1970.
1.5 11/70
- 4. R. M. Hunt, Safety-Related Research and Development for Westinghouse PWRs, Program Summaries. Spring 1970, WCAP-7498-L, May 1970.
1.5 5/70 5. M. D. Davis, Safety-Related Research and Development for Westinghouse PWRs, Program Summaries. Fall 1974, WCAP-8485, March 1975.
1.5 3/75 6. C. J. Kubit, Safety-Related Research and Development for Westinghouse PWRs, Program Summaries. Spring 1974, WCAP-8385, July 1974.
1.5 7/74 7. Deleted
- 8. J. M. Hellman, Fuel Densification Experimental Results and Model for Reactor Operation, WCAP-8218-P-A, March 1975 (Proprietary) and WCAP-8219-A, March 1975 (Non-Proprietary).
1.5 3/75 9. L. Geninski, et al, Safety Analysis of the 17 x 17 Fuel Assembly for Combined Seismic and Loss-of-Coolant Accident, WCAP-8288, December 1973.
1.5 12/73
- 10. E. E. DeMario and S. Nakazato, Hydraulic Flow Test of the 17 x 17 Fuel Assembly, WCAP-8279, February 1974.
1.5 2/74 DCPP UNITS 1 &
2 FSAR UPDATE 1.6-2 Revision 23 December 2016 Date Section Submitted Title Reference To AEC/NRC 11. F. W. Cooper, Jr., 17 x 17 Drive Line Components Test -
Phase IB, II, III - Drop and Deflection, WCAP-8446, December 1974.
1.5 12/74
- 12. K. W. Hill, et al, Effect of 17 x 17 Fuel Assembly Geometry on DNB, WCAP-8296-P-A, February 1975 (Proprietary) and WCAP-8297-A, February 1975.
1.5 2/75 13. F.E. Motley, et al, The Effect of 17 x 17 Fuel Assembly Geometry on Interchannel Thermal Mixing, WCAP-8298-P-A (Proprietary) and WCAP-8299-A, January 1975.
1.5 1/75
- 14. A. J. Burnett and S. D. Kopelic, Westinghouse ECCS Evaluation Model October 1975 Version, WCAP-8622 (Proprietary) and WCAP-8623 (Non-Proprietary),
November 1975.
1.5 11/75
- 15. Irradiation of 17 x 17 Demonstration Assemblies in Surry Units No.1 and 2, Cycle 2, WCAP-8262, July 1974.
1.5 7/74
- 16. G.J. Bohm, Indian Point Unit 2 Internals Mechanical Analysis for Blowdown Exitation, WCAP-7822, December 1971.
3.9 12/20/71
- 17. P. M. Wood, et al, Use of Burnable-Poison Rods in Westinghouse Pressurized Water Reactors, WCAP-7113, October 1967.
3.9 11/6/67 18. R. F. Barry, et al, Power Distribution Monitoring in the R. E.
Ginna PWR, WCAP-7756, September 1971.
3.9 10/5/71 19. L. T. Gesinski, Fuel Assembly Safety Analysis for Combined Seismic and Loss-of-Coolant Accident, WCAP-7950, July 1972.
3.9 7/14/72
- 20. Deleted
- 21. Deleted
DCPP UNITS 1 &
2 FSAR UPDATE 1.6-3 Revision 23 December 2016 Date Section Submitted Title Reference To AEC/NRC 22. S. Kraus, Neutron Shielding Pads, WCAP-7870 including Appendix B, February 1972.
4.2 2/17/72 23. Deleted in Revision 23.
- 24. A. F. McFarlane, Power Peaking Factors, WCAP-7912-P-A, January 1975 (Westinghouse Proprietary) and WCAP-7912-A, January 1975.
4.3, 4.4 3/8/72
- 25. J. A. Christensen, et al, Melting Point of Irradiated Uranium Dioxide , WCAP-6065, February 1965.
4.2, 4.4 2/65 26. G. Hetsroni, Hydraulic Tests of the San Onofre Reactor Model, WCAP-3269-8, June 1964.
4.4 6/64
- 27. G. Hetsroni, Studies of the Connecticut-Yankee Hydraulic Model, WCAP-2761, June 1965, (NYO-3250-2).
4.4 6/65
- 28. J. S. Shefcheck, Application of the THINC Program to PWR Design, WCAP-7359-L, August 1969 (Westinghouse Proprietary) and WCAP-7838, January 1972.
4.4, 15.1, 15.2, 15.4 1/17/72
- 29. F. D. Carter, Inlet Orificing of Open PWR Cores, WCAP-9004, (Westinghouse Proprietary), January 1969, and WCAP-7836, January 1972.
4.4 3/19/69 1/17/72
- 30. J. A. Nay, Process Instrumentation for Westinghouse Nuclear Steam Supply System, WCAP-7671, April 1971.
5.2, 7.1, 7.2, 7.3 5/10/71
- 31. W. O. Shabbits, Dynamic Fracture Toughness Properties of Heavy Section-A-533 Grade B Class I Steel Plate, WCAP-7623, September 1972.
5.2 9/15/72
- 32. W. S. Hazelton, et al, Basis for Heatup and Cooldown Limit Curves, WCAP-7924, July 1972.
5.2 8/14/72
- 33. Deleted
- 34. J. Locante and E. G. Igne, Environmental Testing of Engineered Safety Features Related Equipment (NSSS-Standard Scope), WCAP-7744, Volume 1, August 1971.
6.3 9/14/71 DCPP UNITS 1 &
2 FSAR UPDATE 1.6-4 Revision 23 December 2016 Date Section Submitted Title Reference To AEC/NRC 35. J. B. Lipchak and R. A. Stokes, Nuclear Instrumentation System, WCAP-7669, April 1971.
7.1, 7.2, 7.7 5/6/71 36. D. N. Katz, Solid State Logic Protection System Description, WCAP-7672, June 1971.
7.1, 7.2, 7.3 5/27/71
- 37. J. T. Haller, Engineered Safeguard Final Device or Activator Testing, WCAP-7705, February 1973.
7.1 2/27/73
- 38. Deleted
- 39. R. Bartholomew and J. Lipchak, Test Report, Nuclear Instrumentation System Isolation Amplifier, WCAP-7819, Revision 1, January 1972.
7.2 1/17/72
- 40. W. C. Gangloff, An Evaluation of Anticipated Operational Transients in Westinghouse Pressurized Water Reactors, WCAP-7486, May 1971. 7.2, 15.2 5/21/71
- 41. T. W. T. Burnett, Reactor Protection System Diversity in Westinghouse Pressurized Water Reactors, WCAP-7306, April 1969. 7.2, 15.4 4/9/69
- 42. A. E. Blanchard, Rod Position Monitoring, WCAP-7571, March 1971.
7.7 4/5/71
- 43.
J. J. Loving, In-Core Instrumentation (Flux Mapping System and Thermocouples), WCAP-7607, July 1971.
7.7 7/27/71
- 44. H.G. Hargrove, FACTRAN, A Fortran IV Code for Thermal Transients in a UO 2 Fuel Rod, WCAP-7908-A, December 1989. 15.1,15.2, 15.3,15.4 11/29/83 45. Deleted in Revision 22 46. Deleted in Revision 22
DCPP UNITS 1 &
2 FSAR UPDATE 1.6-5 Revision 23 December 2016 Date Section Submitted Title Reference To AEC/NRC 47. T. W. T. Burnett, et al, LOFTRAN Code Description, WCAP-7907-P-A (Proprietary), April 1984 and WCAP-7907-A (Non-Proprietary), April 1984.
15.1,15.2, 15.3,15.4 10/11/72 48. R. F. Barry, LEOPARD - A Spectrum Dependent Non-Spatial Depletion Code for the IBM-7094, WCAP-3269-26, September 1963.
4.3 9/63
- 49. S. Altomare and R. F. Barry, The TURTLE 24.0 Diffusion Depletion Code, WCAP-7213-P-A, February 1975 (Westinghouse Proprietary) and WCAP-7758-A, February 1975. 4.3 6/68, 9/71
- 50. D. H. Risher, Jr. and R. F. Barry, TWINKLE - A Multi-Dimensional Neutron Kinetics Computer Code, WCAP-7979-P-A (Proprietary) and WCAP-8028-A (Non-
Proprietary), January 1975.
15.1,15.2, 15.4 1/4/73
- 51. Deleted in Revision 22
- 52. Deleted
15.1 6/74
- 54. F. W. Cooper, Jr., 17x17 Drive Line Components Tests Phase IB-II-III D-Loop Drop and Deflection, WCAP-8446 (Proprietary) and WCAP-8449 (Non-proprietary),
(December 1974).
15.1 12/74
- 55.
J. V. Miller (Ed.), Improved Analytical Methods Used in Westinghouse Fuel Rod Design Calculations, WCAP-8720, October 1976.
4.2 10/76
- 56. F. E. Motley and F. F. Cadek, DNB Test Results for New Mixing Vane Grids (R), WCAP-7695-P-A (Proprietary) and WCAP-7958-A (Non-Proprietary), January 1975.
4.4 1/75
- 57. Cooper, et al., Overpressure Protection for Westinghouse Pressurized Water Reactors, WCAP-7769, Revision 1, June 1972.
5.2, 15.2 10/8/71 DCPP UNITS 1 &
2 FSAR UPDATE 1.6-6 Revision 23 December 2016 Date Section Submitted Title Reference To AEC/NRC 58. D.S. Huegel, et al, RETRAN-02 Modeling and Qualification for Westinghouse Pressurized Water Reactor Non-LOCA Safety Analyses, WCAP-14882-P-A (Proprietary), April 1999 and WCAP-15234-A (Non-Proprietary), May 1999.
6.2D, 15.1, 15.2, 15.4 6/6/97 59. M.E. Nissley, et al, Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM), WCAP-16009-P-A, January 2005.
4.3, 15.4 6/2/2003 60. T. Q. Nguyen, et al, Qualification of the PHOENIX-P/ANC Nuclear Design System for Pressurized Water Reactor Cores, WCAP-11596-P-A (Proprietary),June 1988. 4.3, 15.1 11/87
- 61. Y. S. Liu, et al, ANC: A Westinghouse Advanced Nodal Computer Code, WCAP-10965-P-A (Proprietary), September 1986 and WCAP-10966-A (Non-Proprietary),
September 1986.
4.3, 15.1, 15.3 5/86
- 62. S. M. Bajorek, et al, Code Qualification Document for Best Estimate LOCA Analysis, WCAP-12945-P-A, Volume I: Models and Correlations, Revision 2, March 1998. Volume II: Heat Transfer Model Validation, Revision 1, March 1998.
Volume III: Hydrodynamics, Components, and Integral Validation, Revision 1, March 1998.
Volume IV: Assessment of Uncertainty, Revision 1, March 1998. Volume V: Quantification of Uncertainty, Revision 1, March 1998. 15.1, 15.4 5/97
- 63. N. Lee, et al, Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code, WCAP-10054-P-A (Proprietary) and WCAP-10081-A (Non-Proprietary),
August 1985 and, Addendum to the Westinghouse Small Break ECCS Evaluation Model Using the NOTRUMP Code: Safety Injection Into the Broken Loop and COSI Condensation Model, WCAP-10054-P-A, Addendum 2, Revision 1, July 1997 (Westinghouse Proprietary). 15.1, 15.3 11/88 DCPP UNITS 1 &
2 FSAR UPDATE 1.6-7 Revision 23 December 2016 Date Section Submitted Title Reference To AEC/NRC 64. P. E. Meyer, NOTRUMP, A Nodal Transient Small Break And General Network Code, WCAP-10079-P-A (Proprietary) and WCAP-10080-A (Non-Proprietary), August 1985. 15.1, 15.3 11/88
- 65. J. C. Schmertz, et al, Technical Justification for Eliminating Large Primary Loop Rupture as the Structural Design Basis for the Diablo Canyon Units 1 and 2 Nuclear Power Plants, WCAP-13039 (Proprietary) and WCAP-13038 (Non-proprietary), November 1991.
3.6 3/92 DCPP UNITS 1 &
2 FSAR UPDATE 1.6-8 Revision 23 December 2016 1.6.2 MISCELLANEOUS TECHNICAL REPORTS Section
Title
Reference
- 1. H. E. Cramer, et al, "S urvey of the Elevated Line Source," Technical Report, Contract No. DA-42-007-AMC-120(R), GCA Technical Report No. 66-13-G, GCA Corporation, Bedford, Mass., 61 pp., 1967.
2.3 (1) 2. C. R. Dickson, et al, "Aerodynamic Effects of the EBR-II Containment Vessel Complex on Effluent Concentration,"
Proc. of the AEC Meteor. Inf.
Meeting at Chalk River, Ontario, September 11-14, 1967, pp.87-104.
2.3 (1) 3. J. G. Edinger, "The Influence of Terrain and Thermal Stratification of Flow Across the California Coastline," AFCRL-TR-60-438, Final Report, Contract No. AF(604)-5212, University of California, Los Angeles, 1960 2.3 (1) 4. P. A. Leighton, "Geographic Aspects of Air Pollution," Geographic Review, LVI, No. 2, 1966, pp. 153-174.
2.3 (1) 5. J. C. Ulberg, "Meteorological Data for Predicting Inhalation Hazards from Space Unit Launch Operations at Point
Arguello," USNRDL-TR-1112, U.S.
Naval Radiological Defense Laboratory, San Francisco, Ca., 1966, pp. 83.
2.3 (1) 6. H. E. Cramer, et al, "Meteorological Prediction Techniques and Data System," Final Report Contract No. DA-42-007-CML-552, U.S. Army, Dugway Proving Ground, Dugway, Utah, 1964.
2.3 (1) 7. F. Pasquill, Atmospheric Diffusion, D. Van Nostrand Company, Ltd., London, 1962, pp. 190.
2.3
- 8. R. A. Dean, "Thermal Contact Conductance Between U0 2 and Zircaloy-2," CVNA-127, May, 1962.
4.4
- 9. A. M. Ross and R. L. Stoute, "Heat Transfer Coefficient Between U0 2 and Zircaloy-2," NRCL-1552, June, 1962.
4.4
- 10. L. S. Tong, "Prediction of Departure from Nucleate Boiling for an Auxiliary Non-Uniform Heat Flux Distribution," Journal of Nuclear Energy, Vol. 21, 1967, pp. 241-248.
4.4 DCPP UNITS 1 &
2 FSAR UPDATE 1.6-9 Revision 23 December 2016 Section
Title
Reference
- 11. J. Weisman, et al, "Experimental Determination of the Departure from Nucleate Boiling in Large Rod Bundles at High
Pressure," Chem, Eng., Prog. Sump. Ser., 64, No. 82, 1968, pp. 114-125.
4.4
- 12. L. S. Tong, et al, "Critical Heat Flux (DNB) in Square and Triangular Array Rod Bundles," JSME, Semi-International Symposium, Paper No. 256, Tokyo, Japan 1967 4.4
- 13. L. A. Stephan, The Effects of Cladding Material and Heat Treatment on the Response of Waterlogged U0 2 Fuel Rods to Power Bursts, IN-ITR-111, January, 1970.
4.4
- 14. Deleted
- 15. Deleted
- 16. M. A. Styrikovich, et al, Atomnoya Energya, Vol. 17, No. 1, July 1964, pp. 45-49, (Translation in UD 621.039.562.5) 6.2
- 17. W. F. Pasedag and J. L. Gallagher, "Drop Size Distribution and Spray Effectiveness," Nuclear Technology, 10, 1971,
- p. 412. 6.2
- 18. L. F. Parsly, Design Considerations of Reactor Containment Spray Systems, ORNL-TM-2412, Part VII, 1970.
6.2
- 19. W. D. Fletcher, et al, "Post-LOCA Hydrogen Generation in PWR Containments," Journal of American Nuclear Society, June 1970.
6.2
- 20. W. D. Fletcher, et al, "Post-LOCA Hydrogen Generation in PWR Containments," Nuclear Technology 10, 1971, pp. 420-427.
6.2
- 21. H. E. Zittel, Radiation and Thermal Stability of Spray Solutions, ORNL-NSRD Program Bi-Monthly Report for May-June, 1969. ORNL-TM-2663, September 1969.
6.2
- 22. W. B. Cottrell, ORNL Nuclear Safety Research and Development Program Bi-Monthly Report for July-August 1968, ORNL-TM-2368, November 1968.
6.2 DCPP UNITS 1 &
2 FSAR UPDATE 1.6-10 Revision 23 December 2016 Section
Title
Reference
- 23. W. B. Cottrell, ORNL Nuclear Safety Research and Development Program Bi-Monthly Report for September-October 1968, ORNL-TM-2425, p. 53, January 1969.
6.2
- 24. H. E. Zittel and T. H. Row, "Radiation and Thermal Stability of Spray Solutions," Nuclear Technology, 10, 1971, pp. 436-443.
6.2
- 25. A. O. Allen, The Radiation Chemistry of Water and Aqueous Solutions, Princeton, N.J., Van Nostrand, 1961.
6.2
- 26. Deleted
- 27. Deleted
- 28. E. A. J. Eggleton, A Theoretical Examination of Iodine-Water Partition Coefficients, AERE(R)-4887, 1967.
6.2 29. M. E. Meek and B. F. Rider, Summary of Fission Product Yields for U-235, U-238, Pu-239, and Pu-241 at Thermal, Fission Spectrum and 14 Mey Neutron Energies, APED-5398, March 1, 1968.
11.1
- 30. J. J. DiNunno, et al, Calculation of Distance Factors for Power and Test Reactor Sites, TID-14844, March 23, 1962.
6.2, 11.1
- 31. J. O. Blomeke and M. F. Todd, Uranium-235 Fission - Product Production as a Function of Thermal Neutron Flux, Irradiation Time, and Decay Time, ORNL-2127, August 19, 1957.
11.1
- 32. F. J. Perkins and R. W. King, "Energy Release from the Decay of Fission Products," Nuclear Science and Engineering,1958.
11.1
- 33. D. F. Toner and J. S. Scott, Fission Product Release from UO 2 Nuclear Safety, Volume 3, No. 2, December 1961.
11.1 34. J. Belle, "Uranium Dioxide: Properties and Nuclear Applications," Naval Reactor, DRD of NRC, 1961.
11.1 DCPP UNITS 1 &
2 FSAR UPDATE 1.6-11 Revision 23 December 2016 Section
Title
Reference
- 35. S. G. Gillespie and W. K. Brunot, "EMERALD NORMAL - A Program for the Calculation of Activity Releases and Doses
from Normal Operation of a Pressurized Water Plant,"
Program Description and User's Manual, Pacific Gas and Electric Company, January 1973. (Provided to AEC
in 1973.)
11.1, 11.2, 11.3, 12.1, 15.5 36. Deleted in Revision 1.
- 37. A. B. Sisson, et al, "Evaluation for Removal of Radio-nuclides from PWR Steam Generator Blowdowns," International Water Conference, November 2, 1971.
11.2
- 38. Deleted
- 39. Deleted
- 40. Deleted
- 41. W. K. Brunot, EMERALD - A Program for the Calculation of Activity Releases and Potential Doses From a Pressurized Water Reactor Plant, Pacific Gas and Electric Company, October 1971. (Provided to AEC in 1971.)
6.2 42. L. S. Tong, "Prediction of Departure from Nucleate Boiling for an Axially Non-Uniform Heat Flux Distribution,"
J. Nuclear Energy, 21, 1967, pp. 241-248.
4.4 43. F. W. Dittus and L. M. K. Boelter, University of California (Berkeley), Public Eng., 1930, 2,433.
4.4, 15.4
- 44. W. H. Jens and P. A. Lottes, Analysis of Heat Transfer, Burnout, Pressure Drop, and Density Data for High Pressure Water, USAEC Report ANL-4627, 1951.
15.4
- 45. T. G. Taxelius, ed. Annual Report - Spert Project, October 1968 September 1969. Idaho Nuclear Corporation, IN-1370, June 1970.
15.4
- 46. R. C. Liimatainen and F. J. Testa, Studies in TREAT of Zircaloy-2-Clad, UO 2 Core Simulated Fuel Elements, ANL-7225, January-June 1966, November, 1966, p. 177.
15.4 DCPP UNITS 1 &
2 FSAR UPDATE 1.6-12 Revision 23 December 2016 Section
Title
Reference
- 47. Regulatory Guide 1.109, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, Revision 1, October 1977.
11.2, 11.3, 11.6 Note 1. These technical reports were originally referenced in FSAR Amendment 85, Appendices 2.3A and 2.3B (refer to Section 2.3.3.1).
1.6.3 DRAWINGS INCORPORATED BY REFERENCE Controlled engineering drawings were removed from the UFSAR at Revision 15. The drawings are considered incorporated by reference. Table 1.6-1 identifies the controlled
engineering drawings that are incorporated by reference and also provides a cross-reference of the controlled engineering drawings to the respective UFSAR figure number. The contents of the drawings are controlled by DCPP procedures.
DCPP UNITS 1 & 2 FSAR UPDATE TABLE 1.3-1 Sheet 1 of 4 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED.
Revision 23 December 2016 DESIGN COMPARISON OF DIABLO CANYON POWER PLANT UNITS 1 & 2, ZION STATION, AND TROJAN NUCLEAR PLANT (Historical-valid through March 1984)
Chapter Number System/Component Section Reference
Discussion 1 Introduction 1.1 All are 4-loop plants Reactor power ratings (Core thermal output):
Diablo Canyon Unit 1:
3338 MWt Diablo Canyon Unit 2 & Trojan: 3411 MWt Zion: 3250 MWt 3 Containment 3.8.2 All containments are steel-lined concrete structures. Diablo Canyon uses conventional reinforcing; Trojan and Zion are posttensioned. Comparative dimensions and designed pressures are:
Design I.D., ft Net Vol, cu ft Press, psig Diablo Canyon 140 2,630,000 47 Trojan 124 2,000,000 60 Zion 140 2,860,000 47 4 Reactor 4.2.1 Generally similar to Zion and Trojan, but differences exist in design based on nuclear and thermal-hydraulic design parameters.
Reactor Vessel 4.2.2 Diablo Canyon Unit 1: Design of thermal shields and upper and lower Internals support structures, etc., is similar to Zion.
Diablo Canyon Unit 2: Design of neutron pads and upper and lower support structures, etc., is similar to Trojan.
Reactivity Control 4.2.3 Similar to Zion and Trojan.
DCPP UNITS 1 & 2 FSAR UPDATE TABLE 1.3-1 Sheet 2 of 4 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED.
Revision 23 December 2016 Chapter Number System/Component Section Reference
Discussion 4
(Cont'd) Nuclear Design 4.3 Similar to Zion and Trojan except differences exist in fuel burnup rates, fuel enrichments, keff, and core kinetics characteristics. Thermal-hydraulic Design 4.4 Similar to Zion and Trojan except for rating differences.
5 Reactor Coolant System 5.1, 5.2, 5.3, 5.4, 5.5 All three plants are similar in design except Diablo Canyon will use codes that specifically apply. Zion has loop stop valves.
Reactor Vessel 5.4 Diablo Canyon Units 1 and 2 each have 50-year design life while Trojan and Zion are designed for 40 years.
Diablo Canyon Unit 2, Trojan, and Zion have four of the inner CRDM housings moved into the outer rows as compared to Diablo Canyon Unit 1. All have the same number of CRDM housings. Diablo Canyon Unit 1 uses ASME Code,Section III, 1965 Edition and addenda through winter 1966. Zion uses ASME Code,Section III, 1965 Edition and addenda through summer 1966. Diablo Canyon Unit 2 and Trojan use ASME Code,Section III, 1968 Edition.
Diablo Canyon Unit 1 and Zion have blowout collars on bottom tubes only. Diablo Canyon Unit 2 does not have blowout collars.
Trojan has blowout collars on control rod drive mechanisms and bottom tubes. Reactor Coolant Pumps 5.5.1 Diablo Canyon Units 1 and 2 and Trojan have spacer couplings. Zion does not.
DCPP UNITS 1 & 2 FSAR UPDATE TABLE 1.3-1 Sheet 3 of 4 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED.
Revision 23 December 2016 Chapter Number System/Component Section Reference
Discussion 5 (Cont'd) Steam Generators 5.5.2 Diablo Canyon and Zion have 1,100 psia secondary side design pressure. Trojan uses 1,200 psia.
Reactor Coolant Piping 5.5.3 Diablo Canyon Units 1 and 2 and Zion use seamless forged pipe sections and 90° elbows which are cast sections joined by electroslag welds. Trojan uses centrifugally cast pipe sections.
Zion's design is modified to accommodate the loop stop valves.
Diablo Canyon and Zion are designed to B31.1. Trojan is designed to B31.7.
Residual Heat Removal System 5.5.6 All are similar in design.
Pressurizer 5.5.10 Head material is cast for Diablo Canyon Unit 1 and Zion while it is fabricated plate for Diablo Canyon Unit 2 and Trojan. The shell material is fabricated plate for all four units.
6 Containment Spray System 6.2.3 All are similar in design.
Emergency Core Cooling
System 6.3 All are similar in design.
7 Reactor Trip System 7.2 Diablo Canyon Units 1 and 2 and Trojan have solid-state logic protection systems while Zion has relay protection. The logic on trips associated with the reactor coolant pump power supplies is similar at Diablo Canyon Units 1 and 2 and Trojan. Zion is different because it has four separate buses, one for each pump, while Diablo Canyon and Trojan have two reactor coolant pumps per bus.
Engineered Safety Features
Actuation System 7.3 All four units have extended engineered safety features testability. Diablo Canyon Units 1 and 2 and Trojan have 2/3 high DCPP UNITS 1 & 2 FSAR UPDATE TABLE 1.3-1 Sheet 4 of 4 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRED TO BE REVISED.
Revision 23 December 2016 Chapter Number System/Component Section Reference
Discussion containment pressure logic for safety injection initiation, while Zion uses 2/4 high containment pressure.
7 (Cont'd) Systems Required for Safe Shutdown 7.4 System functions are similar on all four units.
Safety-related Display Instrumentation 7.5 Parametric display is similar for all four units. The physical configuration may differ.
Other Safety Systems 7.6 All four units have residual heat removal isolation valve interlocking and automatic closure devices.
Control Systems 7.7 Diablo Canyon Units 1 and 2 and Trojan have digital rod position indication systems, while Zion has analog rod position indication.
8 Electric Power Fig. 8.1-1 Diablo Canyon and Trojan auxiliary systems supply loads at 12 and 4.16 kV. Zion does not have 12-kV loads.
Standby Power 8.3.2 Trojan has two 4.16-kV ESF buses with one standby diesel generator unit (two engines in line per unit) on each bus. Diablo Canyon and Zion have five standby diesel generators, two for each unit and one that can be transferred to either unit.
9 Chemical and Volume 9.3.4 Similar, except Diablo Units 1 and 2 and Zion have 12 percent boric acid concentration systems, while Trojan has a 4 percent system. 10 Steam and Power Conversion System 10.2 Turbines are similar with three double-flow low pressure elements and six stages of feedwater heating.
11 Radioactive Waste Management Entire chapter Systems and treatment provided are similar.
DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.3-2 Sheet 1 of 4 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016 MAJOR DESIGN CHANGES SINCE THE PSAR (Historical-valid through July 1974)
Item Changes in Design Original FSAR Section References 1. Reactor vessel internals changes (Unit 2) - Thermal shield replaced by neutron pads, and lower core support plate and upper internals support system redesigned.
4.2.2 2. Tetra boron carbide control rod poison material changed to silver-indium-cadmium.
4.2.3 3. Pellet density, fuel rod pressure, and burnable poison loading pattern have changed to reflect more detailed design calculations and latest operating experience.
4.3 4. Reactor vessel top and bottom head penetration and control rod drive mechanisms have been redesigned and removable insulation has been provided on the closure head to enable inservice inspection. 4.3, 5.4, 5.4.2, 5.4.4 5. Safety injection now provides cold leg injection with cold leg or hot leg recirculation.
6.3 6. Rod withdrawal step from rod drop signal and automatic turbine load cutback initiated by rod drop have been replaced by the power range neutron flux rate trips.
7.2 7. Relay logic for reactor protection and engineered safety features actuation system has been changed to solid-state
logic. 7.2, 7.3 8. On-line testing has been provided for engineered safety features actuation system.
7.3 9. Analog rod position indication has been replaced by digital rod position indication.
7.7.1 10. Deleted in Revision 15 11. Design criteria changes in the event of inleakage of contaminated water into component cooling water (CCW) system. This tends to minimize possible release of reactor coolant outside containment via the CCW system.
9.2.2 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.3-2 Sheet 2 of 4 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016
Item Changes in Design Original FSAR Section References 12. The compressed air system is revised to eliminate the emergency air system. This satisfies safety criteria while reducing potential leakage paths from containment.
9.3.1 13. The stainless steel liner in the spent fuel pool and transfer canal is changed from Design Class I to Design Class II. The liners prevent minor leakage, and the pool and canal structures remain Design Class I and are relied upon to prevent major failure.
9.1.2 14. The primary water storage tank is reclassified from Design Class I to Design Class II. This is no longer the primary source of makeup water to the CCW System. A backup source to a makeup supply to a Design Class I system itself need not be classified Design Class I.
9.2.4 15. The detectors for the fire detection alarm system are relocated to give more specific identification of the location of the source. Instrument ac power is provided.
9.5.1 16. In the containment structure, vertical joints are provided with a shear key, as required by ACI 301-66.
3.8.2 17. The Chief Mechanical Engineer is no longer the designated Project Engineer. This change was made April 26, 1971.
17.0 18. Those parts of the fire protection system that protect Design Class II and III equipment and structures are not required to
be Design Class I.
9.5.1 19. Inspection procedures for cable were modified to require tests on sample reels from each production run, rather than on each reel.
8.5.2 20. The fuel assembly array is revised from 15 x 15 to 17 x 17. The change was initiated to maintain sufficient flexibility to fulfill the requirements of, or any changes to, 10 CFR 50.46: "Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors." 4 and 15 21. The steam generator blowdown treatment system is added to provide for treatment in the event that there is primary-to-
secondary leakage.
11.2.2 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.3-2 Sheet 3 of 4 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016
Item Changes in Design Original FSAR Section References 22. An alarm system is added to indicate the rupture of a auxiliary seawater cooling header. The function of the alarm is to alert the operator in the event that the header breaks, so that the operator can route the cooling water to the redundant supply header and restore the cooling function to the CCW system. 9.2 23. The turbine building is protected from floods due to pipe breaks by the addition of an 18-inch overflow drain from the sump system to the circulating water discharge canal.
9.2 24 Protection against flooding of the turbine building is provided by design changes to decrease the probability of rupturing
the expansion joints at the water box. Also, the consequences of a rupture are minimized by the addition of expansion joint sleeves.
10.4 25. A system is added and designed to detect and alarm in the event that there are loose parts in the reactor coolant system.
3.9 26. A Design Class I supply of demineralized water is provided for makeup to the spent fuel pool.
9.1 27. The ventilation system for the fuel handling area is modified and reclassified to Design Class I.
9.4 28. A Design Class I containment hydrogen purge system is provided for reducing the containment atmosphere hydrogen concentration in the event of a LOCA. The system has redundant sets of supply and exhaust fans and filters. Each fan is on a separate vital bus.
6.2 29. The heating, ventilating, and air conditioning system for the control room is modified and is reclassified as Design Class I.
The system has four modes of operation designed to make the control room habitable: (a) during normal operation,(b) during long-term occupancy, (c) in the event that there is excessive airborne activity external to the control room, and (d) in the event that there is a fire in the control room.
9.4 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.3-2 Sheet 4 of 4 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016
Item Changes in Design Original FSAR Section References 30. Design changes add the capability of maintaining reactor coolant system temperature during hot shutdown operations; when the reactor is subcritical, the steam dumps to the main condenser. This is accomplished by a controller in the steam line, operating in the pressure control mode, which is set to maintain the steam generator steam pressure.
5.1 31. Meteorological monitoring equipment will provide data to be recorded in the control room during plant operation.
16.4
DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.4-1 Sheet 1 of 3 HISTORICAL INFORMATION IN ITALI CS BELOW NOT REQUIRED TO BE REVISED Revision 23 December 2016 PRINCIPAL CONSULTANTS AND CONTRACT DESCRIPTION (Historical-valid through March 1986)
Principal Consultant Contract (Over $100,000)
Anco Engineers, Inc. Raceway system qualification; seismic testing of mechanical equipment
Arremany & Associates Nondestructive examination services
Associated Technical Training Services Operator training
Babcock & Wilcox, Inc. Engineering support
Bechtel Power Corporation Project management, engineering, construction procurement, startup, project cost and scheduling, quality assurance
J. R. Benjamin and Associates, Inc. Seismic verification of auxiliary and turbine buildings; frequency of vessel impact on intake structure William K. Brunot Reliability and risk analysis
Burns & Roe, Inc. Engineering quality control services
California Department of Fish and Game Marine biology studies
California Polytechnic State University Marine biology studies
Chemrad Corporation Radiological and health physics support
Cygna Energy Services, Inc. Piping support and HVAC equipment qualification Earth Sciences Associates Geological investigations
Ecological Analysts, Inc. Marine biology studies
DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.4-1 Sheet 2 of 3 HISTORICAL INFORMATION IN ITALI CS BELOW NOT REQUIRED TO BE REVISED Revision 23 December 2016 Principal Consultant Contract (Over $100,000)
EDS Nuclear, Inc. Control room (HVAC) design, technical support center pressurization system design, piping anchors design review, radiation shielding design review, emergency core cooling system nozzle fatigue analysis Energy Training Corporation Operator training
Geri Engineering, Inc. Reactor vessel inservice inspection tool modification
Harding - Lawson Associates Soil investigations, geophysical surveys
Hydro - Research Science Discharge structure model study
Innova Corporation Pipe support design review and redesign engineering James Engineering Company Engineering support
Kaiser Engineers, Inc. Program management and engineering services, independent assessment of alternative cooling water systems
Lambert & Company Nondestructive examination services
Nuclear Services Corporation Pipe break analysis
Nucon, Inc. Engineering support for fuel load and startup
NUS Corporation Engineering studies of spent fuel pool storage expansion
Nutech Engineers, Inc. Seismic and environmental qualification engineering support
Offshore Technology Corporation Intake structure hydraulic model studies Omar J. Lillevang Breakwater design, breakwater damage study DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.4-1 Sheet 3 of 3 HISTORICAL INFORMATION IN ITALI CS BELOW NOT REQUIRED TO BE REVISED Revision 23 December 2016 Principal Consultant Contract (Over $100,000)
Pickard, Lowe, & Garrick, Inc. Probabilistic risk assessment
Project Assistance Corporation Quality assurance program support
Radiation Research Associates, Inc. Shielding design review
Regents of the University of California Thermal physical modeling studies
R. F. Reedy and Associates Quality assurance verification
Robert L. Cloud Associates, Inc. Hosgri seismic reverification program
Stone & Webster Engineering Corporation Independent design verification program -
Phase II TERA Corporation Source modeling studies, general engineering, thermal discharge assessment, assessment of alternative cooling water systems
Terra Technology Corporation Seismic recording system maintenance and records processing
Teledyne Engineering Services Independent design verification program
URS/John A. Blume and Associates Seismic structural criteria, electrical seismic testing criteria, seismic research program, seismic review and reverification, independent internal review, Hosgri seismic evaluation
Waltek Services Technical support services
Westinghouse Electric Corporation Long-term seismic research program, environmental qualification, piping redesign and qualification, seismic reverification technical
support Woodward - Clyde and Associates Seismic surveys Wyle Laboratories Seismic test and engineering support
DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.4-2 Sheet 1 of 3 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016 SUPPLIERS OF IMPORTANT EQUIPMENT AND MATERIALS OTHER THAN NUCLEAR STEAM SUPPLY SYSTEM (Historical-valid through March 1986)
Supplier Equipment/Materials Alco Engines Division, White Industrial Power, Inc. Diesel generator units
American Bridge Co., Division of U.S. Steel
Corp. Furnish structural steel AMF Cuno Division Radioactive waste filters
Armco Steel Corp. Containment wall penetration flued heads
Babcock & Wilcox Safety parameter display system Berkeley Steel Construction Co. Radioactive waste tanks
Bingham-Willamette Pump Co. Component cooling water pumps, auxiliary saltwater pumps
Byron Jackson Pump, Division of Borg-
Warner Corp. Auxiliary feedwater pumps
Capital Westward Inc. Radioactive waste tanks
Chem-Nuclear Services Inc. Radioactive resin removal and transfer system
Chemetron Corp. Carbon dioxide
Combustion Engineering Subcooled margin monitor Contromatics Corp. Radioactive waste valves
De Laval Turbine Inc. Diesel fuel transfer pumps
Dresser Industries Inc. Steam generator safety valves Fairbanks-Morse Co. Fire pumps
DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.4-2 Sheet 2 of 3 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016 Supplier Equipment/Materials Fenwall Inc. Halon 1301 system
Fisher Controls Co. Class I pressure/level controllers, and control valves Fulton Shipyard Fuel handling area crane
General Electric Co. Electrical penetrations of containment structure, 12 and 4.16-kV switchgear Grinnell Co. Radioactive waste valves
Harnischfeger P&H Turbine building bridge cranes
Ingersoll-Rand Co. Radioactive waste pumps, reactor coolant drain tank pump, makeup water system pumps
J. E. Lonergan Co. Class I safety relief valves
Mine Safety Appliances Co. Radwaste gas analyzers Murphy Pacific Corp. Furnish structural steel
M. W. Kellogg Co. (Pullman Power
Products) Main systems piping National Controls, Inc. Condensed waste drumming system
Paul Monroe Hydraulics Dome service crane snubbers
Pyrotronics, Inc. Fire detection and alarm system Quick Manufacturing Co. Dome service crane
Schutte and Koerting Co. Main steam isolation and check valves
Scott Company of California Ventilation and air filters, fire water and stand pipe system DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.4-2 Sheet 3 of 3 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016 Supplier Equipment/Materials Velan Valve Corp. Radioactive waste valves
Viking Automatic Sprinkler Co., Chemtron
Corp. (Subcontractor) Water spray and CO 2 fire protection systems
Westinghouse Electric Corp. Radioactive waste evaporators
Yuba Manufacturing Co. Component cooling water heat exchanger, polar crane DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.4-3 Sheet 1 of 3 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016 CONSTRUCTION AND INSTALLATION CONTRACTORS (Historical-valid through March 1986)
Contractor Units 1 and 2 In-progress Contracts Over $100,000
Bechtel Construction Inc. Plant maintenance Plant Asbestos - Thorpe Insulation Furnish and install insulation
Promatec Furnish and install insulation
Pullman Power Products Erect plant and steam piping Westinghouse Electric Corporation Erect turbine-generator
Contractor Units 1 and 2 Completed Contracts Over $100,000 A. J. Diani Construction Paving of access roads
American Bridge Complete structural steel
Ames Associates Repair breakwater Arrowhead Industrial Water Furnish demineralizer
Bigge Crane & Rigging Co. Heavy equipment handling
Bigge Drayage Co. Material receiving/storage (Pismo Beach laydown and storage yard)
Bostrom-Bergen Structural steel
Bovee & Crail Construction Erect intake equipment & pipe Chemtrol Corporation Furnish and install penetration seals
Continental Heller Corp. Construct security building
E.H. Haskell Company Parking lot DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.4-3 Sheet 2 of 3 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016 Contractor Units 1 and 2 Completed Contracts Over $100,000 Endurance Metal Product Co. Erect miscellaneous steel
Granite Constr. Co. and Gordon H. Ball, Inc. Construct breakwaters
Guy F. Atkinson Company Construction of seismic modifications, construct buildings
Healy - Tibbits Repair breakwater
H&H Construction, Inc. Grading and paving (Pismo Beach laydown and storage yard)
H. H. Robertson Co. Install siding and roofing
H.P. Foley Company Install wiring, electrical equipment, and instrumentation. Construct seismic modifications of buildings.
Morgan Equipment Co. Batch plant Murphy Pacific Corp. Furnish and install structural steel erect turbine building cranes Pinkerton's Inc. Security guard service
Pittsburg-Des Moines Steel Co. Fabricate auxiliary building tanks, construct storage tanks Pullman Power Products Construct pipe rupture restraints
Relocate Structures, Inc. Construct administration building
Robert McMullan & Son, Inc. Finish painting
Sanchez & Son, Inc. Grading and paving (Pismo Beach laydown and storage yard)
San Luis Garbage Disposal of waste water DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.4-3 Sheet 3 of 3 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016 Contractor Units 1 and 2 Completed Contracts Over $100,000 Scott Company of California Furnish and install air conditioning and ventilation
System Steel Builders Construction offices, warehouse buildings (Pismo Beach laydown and storage yard)
Tech-Sil, Inc. Furnish and install penetration seals
Valley Trucking of Santa Maria, Inc. Disposal of waste water
Viking Automatic Sprinkler Co. Furnish and install fire protection Walter Bros. Construction Co. and Milburn & Sansome Co. Plant roads and site preparation, construct Harford Drive-County Road construct access road
Wismer & Becker Contracting Engineers Install electrical equipment switchyard, install mechanical equipment/erect NSSS
DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.5-1 Sheet 1 of 3 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016 RESEARCH AND DEVELOPMENT PROGRAMS (Historical-valid through November 1975)
PROGRAM TECHNICAL REPORTS Fuel development for operations at high power densities Full-length emergency core cooling heat transfer tests (FLECHT) Reactor vessel thermal shock Verification test (17 x 17)
Delayed departure from nucleate boiling (DDNB) F. T. Eggleston, Safety-Related Research and Development for Westinghouse PWRs, Program Summaries. Winter 77 - Summer 78, WCAP-8768, Rev.
2, October 1978.
Core stability evaluation Blowdown forces program C. J. Kubit, Safety-Related Research and Blowdown Development for Westinghouse PWRs, Program Summaries. Fall 1972, WCAP-8004, January 1973.
Containment spray Fuel rod burst Loss-of-coolant analysis ESADA DNB R. M. Hunt, Safety-Related Research and Development for Westinghouse PWRs, Program Summaries. Fall 1970, WCAP-7614-L, November 1970.
Burnable poison Flashing heat transfer R. M. Hunt, Safety-Related Research and Development for Westinghouse PWRs, Program Summaries. Spring 1970, WCAP-7498-L, May 1970.
Fuel development for operation at high power densities M. D. Davis, Safety-Related Research and Development for Westinghouse PWRs, Program Summaries. Fall 1974, WCAP-8485, March 1975.
DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.5-1 Sheet 2 of 3 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016 PROGRAM TECHNICAL REPORTS Incore detector Gross failed fuel detector C. J. Kubit, Safety-Related Research and Development for Westinghouse PWRs, Program Summaries. Spring 1974, WCAP-8385, July 1974.
Environmental testing of engineered safety features related equipment C. J. Kubit, Safety-Related Research and Development for Westinghouse PWRs, Program Summaries. Spring 1972, WCAP-7856, May 1972.
In-pile fuel densification J. M. Hellman, Fuel Densification Experimental Results and Model for Reactor Operation, WCAP-8218-P-A March 1975 (Proprietary) and WCAP-8219-A, March, 1975 (Non-proprietary).
Verification test (17 x 17) L. Geninski, et al, Safety Analysis of the 17 x 17 Fuel Assembly for Combined Seismic and Loss-of-Coolant Accident, WCAP-8288, December 1973.
Verification test (17 x 17) E. E. DeMario and S. Makazato, Hydraulic Flow Test of the 17 x 17 Fuel Assembly, WCAP-8279, February 1974.
Verification test (17 x 17) F. W. Cooper, Jr., 17 x 17 Drive Line Components Test - Phase IB, II, II, - Drop and Deflections, WCAP-8446, December 1974.
DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.5-1 Sheet 3 of 3 HISTORICAL INFORMATION IN ITALICS BELOW NOT REQUIRE D TO BE REVISED Revision 23 December 2016 PROGRAM TECHNICAL REPORTS Departure from nucleate boiling (DNB) K. W. Hill, et al, Effect of 17 x 17 Fuel Assembler Geometry on DNB, WCAP-8396-P-A, February 1975 (Proprietary) and WCAP-8297-A, February 1975.
Incore flow mixing F. E. Motley, et al, The Effect of 17 x 17 Fuel Assembly Geometry on Interchannel Thermal Mixing, (WCAP-8298-P-A) (Proprietary) and WCAP-8299-, January 1975.
LOCA heat transfer tests A. J. Burnett and S. D. Kopelic, Westinghouse ECCS Evaluation Model October 1975 Version, WCAP-8622 (Proprietary) and WCAP-8623 (Non-Proprietary), November 1975.
17 x 17 fuel surveillance program Irradiation of 17 x 17 Demonstration Assemblies in Surry Units No. 1 and 2, Cycle 2, WCAP-8262, July 1974.
DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 1 of 28 Revision 23 December 2016 CONTROLLED ENGINEERING DRAWING S/FSAR UPDATE FIGURES CROSS REFERENCE Figure Sheet Drawing Description 1.2-3 500001-1 Area Location Plan 1.2-4 57727-1 Auxiliary, Containment, and Fuel Handling Buildings (Units 1 & 2), Plan at Elevation 140 ft 1.2-5 57726-1 Auxiliary, Containment, and Fuel Handling Buildings (Units 1 & 2), Plan at Elevation 115 ft 1.2-6 57725-1 Auxiliary, Containment, and Fuel Handling Buildings (Units 1 & 2), Plan at Elevations 91 and 100 ft 1.2-7 57724-1 Auxiliary and Containment Buildings (Units 1 & 2), Plan at Elevation 85 ft 1.2-8 57723-1 Auxiliary and Containment Buildings (Units 1 & 2), Plan at Elevation 73 ft 1.2-9 57722-1 Auxiliary and Containment Buildings (Unit 1 & 2), Plan at Elevations 60 and 64 ft 1.2-10 500977-1 Containment Building (Unit 2), Plan at Elevations 115 and 140 ft 1.2-11 500971-1 Containment & Fuel Handling Buildings (Unit 2), Plan at Elevations 85, 91, and 100 ft 1.2-12 500968-1 Containment Building (Unit 2), Plan at Elevations 60, 64, and 73 ft 1.2-13 57721-1 Turbine Building (Unit 1), Plan at Elevation 140 ft 1.2-14 57720-1 Turbine Building (Unit 1), Plan at Elevation 119 ft 1.2-15 57719-1 Turbine Building (Unit 1), Plan at Elevation 104 ft 1.2-16 57718-1 Turbine Building (Unit 1), Plan at Elevation 85 ft 1.2-17 500967-1 Turbine Building (Unit 2), Plan at Elevation 140 ft 1.2-18 500966-1 Turbine Building (Unit 2), Plan at Elevation 119 ft 1.2-19 500965-1 Turbine Building (Unit 2), Plan at Elevation 104 ft 1.2-20 500964-1 Turbine Building (Unit 2), Plan at Elevation 85 ft 1.2-21 57728-1 Auxiliary Building (Units 1 & 2), Section A-A 1.2-22 57729-1 Auxiliary and Containment Buildings (Unit 1 & 2), Section B-B 1.2-23 57730-1 Auxiliary and Fuel Handling Buildings (Unit 1 & 2), Section C-C DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 2 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 1.2-24 57731-1 Containment, Turbine, and Fuel Handling Buildings (Unit 1) Section D-D 1.2-25 57732-1 Auxiliary, Turbine, and Fuel Handling Buildings (Unit 1), Section E-E 1.2-26 57733-1 Auxiliary, Fuel Handling, and Turbine Buildings (Units 1 & 2), Section F-F 1.2-27 57734-1 Turbine Building (Unit 1), Section G-G 1.2-28 500969-1 Containment Building (Unit 2), Section A-A 1.2-29 500972-1 Vent & Fuel Handling Buildings (Unit 2), Section B-B 1.2-30 500973-1 Turbine, Containment, & Fuel Handling Buildings (Unit 2), Section C-C 1.2-31 500974-1 Turbine Building (Unit 2), Sections D-D and E-E 1.2-32 500976-1 Turbine Building (Unit 2), Section F-F 2.4-7 468999-1 Typical Sections for Tribar Armor Construction 2.4-8 469001-1 Restored Cross-sections and Embedment Plan 3.2-1 1 of 4 102001-3 Pi ping Schematic Legend 3.2-1 1A of 4 102023-2 Pi ping Schematic Legend 3.2-1 2 of 4 108001-3 Pi ping Schematic Legend 3.2-1 2A of 4 108023-2 Pi ping Schematic Legend 3.2-2 1 of 23 102002-4 Pipi ng Schematic - Condensate System (23 Sheets) 3.2-2 2 of 23 108002-4 3.2-2 3 of 23 102002-5 3.2-2 3A of 23 102002-5A 3.2-2 4 of 23 108002-5 3.2-2 5 of 23 102002-6 3.2-2 5A of 23 102002-6A 3.2-2 6 of 23 108002-6 3.2-2 7 of 23 102002-7 3.2-2 8 of 23 108002-7 3.2-2 9 of 23 102002-8 3.2-2 9A of 23 102002-8A 3.2-2 10 of 23 108002-8 3.2-2 10A of 23 108002-8A 3.2-2 11 of 23 102002-9 3.2-2 11A of 23 102002-9A DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 3 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-2 11B of 23 102002-9B 3.2-2 12 of 23 108002-9 3.2-2 12A of 23 108002-9A 3.2-2 13 of 23 102002-10 3.2-2 14 of 23 108002-10 3.2-2 15 of 23 102002-11 3.2-2 16 of 23 108002-11 3.2-3 1 of 11 102003-3 Piping Schematic - Feedwater System (11 Sheets) 3.2-3 1A of 11 102003-3A 3.2-3 2 of 11 108003-3 3.2-3 3 of 11 102003-4 3.2-3 4 of 11 108003-4 3.2-3 5 of 11 102003-4A 3.2-3 6 of 11 108003-4A 3.2-3 7 of 11 102003-5 3.2-3 8 of 11 108003-5 3.2-3 9 of 11 102003-6 3.2-3 10 of 11 108003-6 3.2-4 1 of 16 102004-3 Piping Schematic - Turbine Steam Supply System (16 Sheets) 3.2-4 2 of 16 108004-3 3.2-4 3 of 16 102004-4 3.2-4 4 of 16 108004-4 3.2-4 5 of 16 102004-5 3.2-4 6 of 16 108004-5 3.2-4 7 of 16 102004-6 3.2-4 8 of 16 108004-6 3.2-4 9 of 16 102004-7 3.2-4 10 of 16 108004-7 3.2-4 11 of 16 102004-8 3.2-4 12 of 16 108004-8 3.2-4 13 of 16 102004-9 3.2-4 14 of 16 102004-10 3.2-4 15 of 16 108004-9 3.2-4 16 of 16 108004-10 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 4 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-5 1 of 12 102005-2 Piping Schematic - Extraction Steam and Heater Drip System (12 Sheets) 3.2-5 2 of 12 108005-2 3.2-5 3 of 12 102005-3 3.2-5 4 of 12 108005-3 3.2-5 5 of 12 102005-4 3.2-5 6 of 12 108005-4 3.2-5 7 of 12 102005-5 3.2-5 8 of 12 108005-5 3.2-5 9 of 12 102005-6 3.2-5 10 of 12 108005-6 3.2-5 11 of 12 102005-7 3.2-5 12 of 12 108005-7 3.2-6 1 of 10 102006-3 Piping Schematic - Auxiliary Steam System (10 Sheets) 3.2-6 1A of 10 102006-3A 3.2-6 2A of 10 102006-3B 3.2-6 2 of 10 108006-3 3.2-6 3 of 10 102006-4 3.2-6 4 of 10 108006-4 3.2-6 5 of 10 102006-4A 3.2-6 6 of 10 108006-4A 3.2-6 7 of 10 102006-5 3.2-6 8 of 10 108006-5 3.2-7 1 of 9 102007-3 Piping Schematic - Reactor Coolant System (9 Sheets) 3.2-7 2 of 9 108007-3 3.2-7 3 of 9 102007-4 3.2-7 4 of 9 108007-4 3.2-7 5 of 9 102007-5 3.2-7 6 of 9 108007-5 3.2-7 7 of 9 102007-5A 3.2-7 7A of 9 102007-5B 3.2-7 8 of 9 108007-5A 3.2-8 1 of 34 102008-3 Pipi ng Schematic - Chemical and Volume Control System (34 Sheets)
DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 5 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-8 1A of 34 102008-3A 3.2-8 1B of 34 102008-3B 3.2-8 1C of 34 102008-3C 3.2-8 2 of 34 108008-3 3.2-8 3 of 34 102008-4A 3.2-8 4 of 34 108008-4A 3.2-8 5 of 34 102008-4 3.2-8 6 of 34 108008-4 3.2-8 7 of 34 102008-4B 3.2-8 7A of 34 102008-4C 3.2-8 7B of 34 102008-4D 3.2-8 7C of 34 102008-4E 3.2-8 8 of 34 108008-4B 3.2-8 8A of 34 108008-4C 3.2-8 9 of 34 102008-5 3.2-8 10 of 34 108008-5 3.2-8 11 of 34 102008-5A 3.2-8 12 of 34 108008-5A 3.2-8 13 of 34 102008-5B 3.2-8 14 of 34 108008-5B 3.2-8 15 of 34 102008-5C 3.2-8 16 of 34 108008-5C 3.2-8 16A of 34 102008-5D 3.2-8 17 of 34 102008-6 3.2-8 17A of 34 102008-6A 3.2-8 18 of 34 108008-6 3.2-8 19 of 34 102008-7 3.2-8 20 of 34 108008-7 3.2-8 21 of 34 102008-8 3.2-8 21A of 34 102008-8A 3.2-8 22 of 34 108008-8 3.2-8 23 of 34 102008-9 3.2-8 24 of 34 108008-9 3.2-9 1 of 12 102009-3 Piping Schematic - Safety Injection System (12 Sheets) 3.2-9 2 of 12 108009-3 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 6 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-9 3 of 12 102009-4 3.2-9 4 of 12 108009-4 3.2-9 5 of 12 102009-5 3.2-9 5A of 12 102009-5A 3.2-9 6 of 12 108009-5 3.2-9 6A of 12 108009-5A 3.2-9 7 of 12 102009-6 3.2-9 8 of 12 108009-6 3.2-9 9 of 12 102009-7 3.2-9 10 of 12 108009-7 3.2-10 1 of 6 102010-3 Pi ping Schematic - Residual Heat Removal System (6 Sheets) 3.2-10 2 of 6 108010-3 3.2-10 3 of 6 102010-4 3.2-10 4 of 6 108010-4 3.2-10 5 of 6 102010-5 3.2-10 6 of 6 108010-5 3.2-11 1 of 11 102011-2 Piping Schematic - Nuclear Steam Supply Sampling System (11 Sheets) 3.2-11 1A of 11 102011-2A 3.2-11 2 of 11 108011-2 3.2-11 3 of 11 102011-3 3.2-11 4 of 11 108011-3 3.2-11 5 of 11 102011-4 3.2-11 6 of 11 108011-4 3.2-11 7 of 11 102011-5 3.2-11 8 of 11 108011-5 3.2-11 9 of 11 102011-6 3.2-11 10 of 11 108011-6 3.2-12 1 of 2 102012-3 Piping Schematic - Containment Spray System (2 Sheets) 3.2-12 2 of 2 108012-3 3.2-13 1 of 3 102013-2 Pipi ng Schematic - Spent Fuel Pool Cooling System (3 Sheets) 3.2-13 1A of 3 102013-2A 3.2-13 2 of 3 108013-2 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 7 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-14 1 of 17 102014-5 Piping Schematic - Component Cooling Water System (17 Sheets) 3.2-14 2 of 17 108014-5 3.2-14 3 of 17 102014-5A 3.2-14 3A of 17 102014-5B 3.2-14 4 of 17 108014-5A 3.2-14 5 of 17 102014-6 3.2-14 6 of 17 108014-6 3.2-14 7 of 17 102014-6A 3.2-14 8 of 17 108014-6A 3.2-14 9 of 17 102014-7 3.2-14 10 of 17 108014-7 3.2-14 11 of 17 102014-8 3.2-14 12 of 17 108014-8 3.2-14 13 of 17 102014-9 3.2-14 14 of 17 108014-9 3.2-14 15 of 17 102014-10 3.2-14 16 of 17 108014-10 3.2-15 1 of 14 102015-3 Piping Schematic - Service Cooling Water System (14 Sheets) 3.2-15 1A of 14 102015-3A 3.2-15 2 of 14 108015-3 3.2-15 2A of 14 108015-3A 3.2-15 2B of 14 108015-3B 3.2-15 3 of 14 102015-4 3.2-15 3A of 14 102015-4A 3.2-15 4 of 14 108015-4 3.2-15 5 of 14 102015-5 3.2-15 6 of 14 108015-5 3.2-15 7 of 14 102015-6 3.2-15 8 of 14 108015-6 3.2-15 9 of 14 102015-7 3.2-15 10 of 14 108015-7 3.2-16 1 of 21 102016-1 Pipi ng Schematic - Makeup Water System (21 Sheets) 3.2-16 1A of 21 108016-1 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 8 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-16 2 of 21 108016-3 3.2-16 3 of 21 102016-4 3.2-16 4 of 21 108016-5 3.2-16 5 of 21 102016-6 3.2-16 6 of 21 102016-7 3.2-16 7 of 21 102016-8 3.2-16 8 of 21 102016-9 3.2-16 9 of 21 102016-9A 3.2-16 10 of 21 102016-10 3.2-16 11 of 21 102016-11 3.2-16 12 of 21 102016-13 3.2-16 13 of 21 102016-14 3.2-16 14 of 21 102016-16 3.2-16 15 of 21 108016-17 3.2-16 16 of 21 102016-18 3.2-16 17 of 21 108016-19 3.2-16 18 of 21 102016-20 3.2-16 19 of 21 102016-21 3.2-16 19A of 21 102016-21A 3.2-17 1 of 18 102017-3 Piping Schematic - Saltwater Systems (18 Sheets) 3.2-17 1A of 18 102017-3A 3.2-17 1B of 18 102017-3B 3.2-17 2 of 18 108017-3 3.2-17 2A of 18 108017-3A 3.2-17 2B of 18 108017-3B 3.2-17 3 of 18 102017-4 3.2-17 4 of 18 108017-4 3.2-17 5 of 18 102017-5 3.2-17 5A of 18 102017-5A 3.2-17 6 of 18 108017-5 3.2-17 7 of 18 102017-6 3.2-17 7A of 18 102017-6A 3.2-17 7B of 18 102017-6B 3.2-17 8 of 18 108017-6 3.2-17 8A of 18 108017-6A DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 9 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-17 8B of 18 108017-6B 3.2-17 8C of 18 108017-6C 3.2-18 1 of 27 102018 Piping Schematic - Fire Protection Systems (27 Sheets) 3.2-18 1A of 27 102018-2A 3.2-18 1B of 27 102018-2B 3.2-18 2 of 27 108018-2 3.2-18 3 of 27 102018-3 3.2-18 4 of 27 108018-3 3.2-18 4A of 27 108018-3A 3.2-18 5 of 27 102018-4 3.2-18 6 of 27 108018-4 3.2-18 7 of 27 102018-4A 3.2-18 8 of 27 108018-4A 3.2-18 9 of 27 102018-5 3.2-18 9A of 27 102018-5A 3.2-18 10 of 27 108018-5 3.2-18 10A of 27 108018-5A 3.2-18 11 of 27 102018-6 3.2-18 11A of 27 102018-6A 3.2-18 12 of 27 108018-6 3.2-18 12A of 27 108018-6A 3.2-18 13 of 27 102018-7 3.2-18 14 of 27 108018-7 3.2-18 15 of 27 102018-8 3.2-18 16 of 27 108018-8 3.2-18 17 of 27 102018-9 3.2-18 18 of 27 108018-9 3.2-18 19 of 27 102018-19 3.2-18 20 of 27 102018-20 3.2-19 1 of 26 102019-3 Piping Schematic - Liquid Radwaste System (26 Sheets) 3.2-19 2 of 26 108019-3 3.2-19 3 of 26 102019-3A 3.2-19 3A of 26 102019-3B 3.2-19 4 of 26 108019-3A DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 10 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-19 4A of 26 108019-3B 3.2-19 5 of 26 102019-4 3.2-19 6 of 26 108019-4 3.2-19 7 of 26 102019-5 3.2-19 7A of 26 102019-5A 3.2-19 7B of 26 102019-5B 3.2-19 7C of 26 102019-5C 3.2-19 8 of 26 108019-5 3.2-19 8A of 26 108019-5A 3.2-19 8B of 26 108019-5B 3.2-19 9 of 26 102019-6 3.2-19 10 of 26 108019-6 3.2-19 11 of 26 102019-6A 3.2-19 11A of 26 102019-6B 3.2-19 12 of 26 108019-6A 3.2-19 12A of 26 108019-6B 3.2-19 13 of 26 102019-7 3.2-19 14 of 26 108019-7 3.2-19 15 of 26 102019-8 3.2-19 15A of 26 102019-8A 3.2-19 16 of 26 108019-8 3.2-20 1 of 26 102020-3 Pipi ng Schematic - Lube Oil Distribution and Purification System (26 Sheets) 3.2-20 1A of 26 102020-3A 3.2-20 1B of 26 102020-3B 3.2-20 2 of 26 108020-3 3.2-20 2A of 26 108020-3A 3.2-20 2B of 26 108020-3B 3.2-20 3 of 26 102020-4 3.2-20 4 of 26 108020-4 3.2-20 5 of 26 102020-5 3.2-20 6 of 26 108020-5 3.2-20 7 of 26 102020-6 3.2-20 7A of 26 102020-6A 3.2-20 7B of 26 102020-6B 3.2-20 8 of 26 108020-6 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 11 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-20 8A of 26 108020-6A 3.2-20 8B of 26 108020-6B 3.2-20 9 of 26 102020-7 3.2-20 10 of 26 108020-7 3.2-20 11 of 26 102020-8 3.2-20 12 of 26 108020-8 3.2-20 13 of 26 102020-9 3.2-20 14 of 26 108020-9 3.2-20 15 of 26 102020-10 3.2-20 16 of 26 108020-10 3.2-20 17 of 26 102020-11 3.2-20 18 of 26 108020-11 3.2-21 1 of 35 102021-2 Pi ping Schematic - Diesel Engine-Generator Systems (35 Sheets) 3.2-21 2 of 35 108021-2 3.2-21 3 of 35 102021-3 3.2-21 3A of 35 102021-3A 3.2-21 4 of 35 108021-3 3.2-21 4A of 35 108021-3A 3.2-21 4B of 35 108021-3B 3.2-21 5 of 35 102021-4 3.2-21 5A of 35 102021-4A 3.2-21 6 of 35 108021-4 3.2-21 6A of 35 108021-4A 3.2-21 6B of 35 108021-4B 3.2-21 7 of 35 102021-5 3.2-21 8 of 35 108021-5 3.2-21 8A of 35 108021-5A 3.2-21 8B of 35 108021-5B 3.2-21 9 of 35 102021-6 3.2-21 9A of 35 102021-6A 3.2-21 10 of 35 108021-6 3.2-21 10A of 35 108021-6A 3.2-21 10B of 35 108021-6B 3.2-21 11 of 35 102021-7 3.2-21 11A of 35 102021-7A DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 12 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-21 11B of 35 102021-7B 3.2-21 12 of 35 108021-7 3.2-21 12A of 35 108021-7A 3.2-21 12B of 35 108021-7B 3.2-21 13 of 35 102021-8 3.2-21 14 of 35 108021-8 3.2-21 14A of 35 108021-8A 3.2-21 14B of 35 108021-8B 3.2-21 15 of 35 102021-9 3.2-21 16 of 35 108021-9 3.2-21 16A of 35 108021-9A 3.2-21 16B of 35 108021-9B 3.2-22 1 of 16 102022-2 Pipi ng Schematic - Turbine and Generator-Associated Systems (16 Sheets) 3.2-22 2 of 16 108022-2 3.2-22 3 of 16 102022-3 3.2-22 4 of 16 108022-3 3.2-22 5 of 16 102022-4 3.2-22 6 of 16 108022-4 3.2-22 7 of 16 102022-5 3.2-22 7A of 16 102022-5A 3.2-22 8 of 16 108022-5 3.2-22 8A of 16 108022-5A 3.2-22 9 of 16 102022-6 3.2-22 9A of 16 102022-6A 3.2-22 10 of 16 108022-6 3.2-22 10A of 16 108022-6A 3.2-22 11 of 16 102022-7 3.2-22 12 of 16 108022-7 3.2-23 1 of 53 102023-3 Pipi ng Schematic - Ventilation and Air Conditioning Systems (53 Sheets) 3.2-23 2 of 53 108023-3 3.2-23 3 of 53 102023-4 3.2-23 4 of 53 108023-4 3.2-23 5 of 53 102023-5 3.2-23 6 of 53 108023-5 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 13 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-23 7 of 53 102023-6 3.2-23 7A of 53 102023-6A 3.2-23 7B of 53 102023-6B 3.2-23 8 of 53 108023-6 3.2-23 8A of 53 108023-6A 3.2-23 9 of 53 102023-7 3.2-23 10 of 53 108023-7 3.2-23 11 of 53 102023-8 3.2-23 12 of 53 108023-8 3.2-23 13 of 53 102023-9 3.2-23 13A of 53 102023-9A 3.2-23 14 of 53 108023-9 3.2-23 15 of 53 102023-10 3.2-23 16 of 53 108023-10 3.2-23 17 of 53 102023-11 3.2-23 18 of 53 108023-11 3.2-23 19 of 53 102023-12 3.2-23 20 of 53 108023-12 3.2-23 21 of 53 102023-13 3.2-23 21A of 53 102023-13A 3.2-23 22 of 53 108023-13 3.2-23 23 of 53 102023-14 3.2-23 24 of 53 108023-14 3.2-23 24A of 53 108023-15 3.2-23 25 of 53 102023-16 3.2-23 25A of 53 108023-16 3.2-23 26A of 53 102023-17A 3.2-23 26B of 53 102023-17B 3.2-23 26C of 53 102023-17C 3.2-23 26 of 53 102023-17 3.2-23 26D of 53 108023-17 3.2-23 27 of 53 102023-15 3.2-23 28 of 53 102023-19 3.2-23 29 of 53 102023-18 3.2-23 29A of 53 102023-18A DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 14 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-23 29B of 53 102023-18B 3.2-23 29C of 53 102023-18C 3.2-23 29D of 53 102023-18D 3.2-23 29E of 53 102023-18E 3.2-23 29F of 53 102023-18F 3.2-23 30 of 53 108023-18 3.2-23 30A of 53 108023-18A 3.2-23 30B of 53 108023-18B 3.2-23 30C of 53 108023-18C 3.2-23 30D of 53 108023-19 3.2-23 31 of 53 102023-20 3.2-23 32 of 53 108023-20 3.2-24 1 of 2 102024-3 Pipi ng Schematic - Gaseous Radwaste System (2 Sheets) 3.2-24 2 of 2 108024-3 3.2-25 1 of 13 102025-3 Piping Schematic - Compressed Air System (13 Sheets) 3.2-25 1A of 13 102025-3A 3.2-25 1B of 13 102025-3B 3.2-25 2 of 13 108025-3 3.2-25 3 of 13 102025-4 3.2-25 3A of 13 102025-4A 3.2-25 4 of 13 108025-4 3.2-25 5 of 13 102025-5 3.2-25 6 of 13 108025-5 3.2-25 7 of 13 102025-6 3.2-25 8 of 13 108025-6 3.2-25 8A of 13 102025-8 3.2-25 9 of 13 108025-8 3.2-26 1 of 5 102026-3 Piping Schematic - Nitrogen and Hydrogen System (5 Sheets) 3.2-26 1A of 5 102026-3A 3.2-26 2 of 5 108026-3 3.2-26 3 of 5 102026-4 3.2-26 4 of 5 108026-4 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 15 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.2-27 1 of 2 102027-3 Piping Schematic - Oily Water Separator and Turbine Building Sump System (2 Sheets) 3.2-27 2 of 2 108027-3 3.5-6 505481-1 Auxiliary Feedwater Pump Turbine Missile Shield 3.6-2 1 of 2 438288-1 Containment Structure Pipe Rupture Restraints (2 sheets) 3.6-2 2 of 2 443359-1 3.6-5 515939-1 HELB Compartment Pressurization Study El. 85 ft Turbine Building 3.6-6 515940-1 HELB Compartment Pressurization Study El. 104 ft Turbine Building 3.6-7 515941-1 HELB Compartment Pressurization Study El. 119 ft Turbine Building 3.6-8 515942-1 HELB Compartment Pressurization Study El. 140 ft Turbine Building 3.6-9 515943-1 HELB Compartment Pressurization Study El. 60 ft Auxiliary and Containment Building 3.6-10 515944-1 HELB Compartment Pressurization Study El. 73 ft Auxiliary and Containment Building 3.6-11 515945-1 HELB Compartment Pressurization Study El. 85 ft Auxiliary and Containment Building 3.6-12 515946-1 HELB Compartment Pressurization Study El. 91 and 100 ft Auxiliary, Containment and Fuel Handling Bldg 3.6-13 515947-1 HELB Compartment Pressurization Study El. 115 ft Auxiliary, Containment and Fuel
Handling Bldg 3.6-14 515948-1 HELB Compartment Pressurization Study El. 140 ft Auxiliary, Containment and Fuel
Handling Bldg 3.6-15 515949-1 HELB Compartment Pressurization Study Section A-A Auxiliary Bldg 3.8-16 1 of 2 443252-1 Interior Concrete Outline - Plan at El. 119 ft and 140 ft, Containment Structure Areas G and F (2 sheets) 3.8-16 2 of 2 438233-1 3.8-17 1 of 2 443254-1 Interior Concrete Outline Main Sections Containment Structure (2 sheets) 3.8-17 2 of 2 438234-1 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 16 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.8-18 1 of 2 443276-1 Interior Concrete Reinforcing Typical Details and Drawing List Containment Structure (2 sheets) 3.8-18 2 of 2 438231-1 3.8-19 1 of 4 443277-1 Inte rior Concrete Reinforcing Sections and Details Containment Structure (4 sheets) 3.8-19 2 of 4 438239-1 3.8-19 3 of 4 438240-1 3.8-19 4 of 4 438242-1 3.8-20 1 of 2 443370-1 C oncrete Outline and Reinforcing Annulus Platform at El. 140 ft, Containment Structure
Areas F and G (2 sheets) 3.8-20 2 of 2 447254-1 3.8-23 438267-1 Containment Structure, Polar Crane 3.8-45 438431-1 Auxiliary Building, Concrete Outline - Plan at El. 100 ft Areas H and K 3.8-46 1 of 2 438432-1 Auxiliary Building, Concrete Outline - Plan at El. 115 ft Areas J, GE, and GW (2 sheets) 3.8-46 2 of 2 439533-1 3.8-47 1 of 3 438449-1 Auxiliary Building, Concrete Outline - Plans at El. 85, 100, 115, and 140 ft - Area L (3 sheets) 3.8-47 2 of 3 443204-1 3.8-47 3 of 3 443205-1 3.8-48 438445-1 Auxiliary Building, Concrete Outline - Section Areas J and K 3.8-49 438441-1 Auxiliary Building, Concrete Outline - Section Areas H and K 3.8-50 1 of 2 438457-1 Auxiliary Building, Concrete Reinforcing - Plan at El. 115 ft - Areas J, GE, and GW (2 sheets) 3.8-50 2 of 2 443227-1 3.8-51 438458-1 Auxiliary Building, Concrete Reinforcing - Plan at El. 115 ft - Areas H and K 3.8-52 443216-1 Auxiliary Building, Concrete Reinforcing - Plans at El. 115 and 140 ft - Area L 3.8-53 443460-1 Auxiliary Building, Concrete Reinforcing - Miscellaneous Sections - Area K 3.8-54 438471-1 Auxiliary Building, Concrete Reinforcing - Section Areas H, K, and GE 3.8-55 438465-1 Auxiliary Building, Control Room - Sections DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 17 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 3.8-56 438474-1 Auxiliary Building, Spent Fuel Pool - Concrete Reinforcing 3.8-57 439506-1 Auxiliary Building, Crane Support Structure - Elevations and Details 3.8-58 439507-1 Auxiliary Building, Crane Support Structure - Section and Details 3.8-59 439509-1 Auxiliary Building, Refueling Areas Overhead Crane 3.8-65 1 of 2 438034-1 De sign Class I Tanks Concrete Foundations (2 Sheets) 3.8-65 2 of 2 463987-1 3.8-72 1 of 2 59459-1 Concrete Outline Plan - Top Deck Area 1 Intake Structure 3.8-72 2 of 2 59460-1 Concrete Outline Plan - Top Deck Area 2 Intake Structure 3.8-73 1 of 2 59461-1 Concrete Outline Plan - Pump Deck Area 1 Intake Structure 3.8-73 2 of 2 59462-1 Concrete Outline Plan - Pump Deck Area 2 Intake Structure 3.8-74 1 of 2 59463-1 Concrete Outline Plan - Invert Area 1 Intake Structure 3.8-74 2 of 2 59464-1 Concrete Outline Plan - Invert Area 2 Intake Structure 3.8-83 515213-1 Safety Related Masonry Walls, Turbine Bldg -
Unit 1 3.8-84 515214-1 Safety Related Masonry Walls, Turbine Bldg -
Unit 2 3.8-85 515215-1 Safety Related Masonry Walls, Auxiliary Bldg 5.5-13 500825-1 U1: Function Diagram, Reactor-Turbine Generator Protection 5.5-17 500800-1 U2: Function Diagram, Reactor-Turbine Generator Protection 6.3-6 6023231-1 DCPP1 Strainer Installation 6.3-7 6023231-20 DCPP2 Strainer Installation 6.5-1 107031-4 Auxiliary Feedwater System 6.5-2 107031-1A Long Term Cooling Water System 7.2-1 1 of 36 495841-1 Instrumentation and Control System Logic Diagrams (36 Sheets) 7.2-1 2 of 36 495871-1 7.2-1 3 of 36 495842-1 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 18 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 7.2-1 4 of 36 495872-1 7.2-1 5 of 36 495843-1 7.2-1 6 of 36 495873-1 7.2-1 7 of 36 495844-1 7.2-1 8 of 36 495874-1 7.2-1 9 of 36 495845-1 7.2-1 10 of 36 495875-1 7.2-1 11 of 36 495846-1 7.2-1 12 of 36 495876-1 7.2-1 13 of 36 495847-1 7.2-1 14 of 36 495877-1 7.2-1 15 of 36 495848-1 7.2-1 16 of 36 495878-1 7.2-1 17 of 36 495849-1 7.2-1 18 of 36 495879-1 7.2-1 19 of 36 495850-1 7.2-1 20 of 36 495880-1 7.2-1 21 of 36 495851-1 7.2-1 22 of 36 495881-1 7.2-1 23 of 36 495852-1 7.2-1 24 of 36 495882-1 7.2-1 25 of 36 495853-1 7.2-1 26 of 36 495883-1 7.2-1 27 of 36 495854-1 7.2-1 28 of 36 495884-1 7.2-1 29 of 36 495855-1 7.2-1 30 of 36 495885-1 7.2-1 31 of 36 495856-1 7.2-1 32 of 36 495886-1 7.2-1 33 of 36 495857-1 7.2-1 34 of 36 495887-1 7.2-1 35 of 36 495858-1 7.2-1 36 of 36 495888-1 7.3-1 19425-1 Logic Diagram Symbols DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 19 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 7.3-2 1 of 2 338070-1 Logic Diagram - Reactor Coolant Pump (2 sheets) 7.3-2 2 of 2 102787-1 7.3-3 1 of 2 19404-1 Logi c Diagram - Centrifugal Charging Pump (CCP3) (2 sheets) 7.3-3 2 of 2 102788-1 7.3-4 1 of 2 19405-1 Logic Diagram - Centrifugal Charging Pumps (CCP1 and CCP2) (2 sheets) 7.3-4 2 of 2 102789-1 7.3-5 1 of 2 19406-1 Logic Diagram - Auxiliary Saltwater Pumps (2 sheets) 7.3-5 2 of 2 102790-1 7.3-6 1 of 2 19407-1 Logic Diagram - Containment Fan Coolers (2 sheets) 7.3-6 2 of 2 102791-1 7.3-7 1 of 2 19408-1 Logic Diagram - Component Cooling Water Pumps (2 sheets) 7.3-7 2 of 2 102792-1 7.3-8 1 of 2 19409-1 Logic Diagram - Auxiliary Feedwater Pumps (2 sheets) 7.3-8 2 of 2 102800-1 7.3-9 19410-1 Logic Diagram - Residual Heat Removal Pumps (2 sheets) 7.3-9 2 of 2 102793-1 7.3-10 1 of 2 19411-1 Logic Diagram - Safety Injection Pumps (2 sheets) 7.3-10 2 of 2 102794-1 7.3-11 1 of 2 19412-1 Logic Diagram - Containment Spray Pumps (2 sheets) 7.3-11 2 of 2 102795-1 7.3-12 1 of 2 19413-1 Logic Diagram - Primary Makeup Water Pumps (2 sheets) 7.3-12 2 of 2 102796-1 7.3-13 1 of 2 19414-1 Logic Diagram - Boric Acid Transfer Pumps (2 sheets) 7.3-13 2 of 2 102797-1 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 20 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 7.3-14 1 of 2 437507-1 Schematic Diagram - Auxiliary Feedwater Motor-Operated Valves (2 sheets) 7.3-14 2 of 2 441301-1 7.3-15 1 of 2 437551-1 Schematic Diagram - Turbine Control (2 sheets) 7.3-15 2 of 2 441253-1 7.3-16 1 of 2 437567-1 Schematic Diagram - Feedwater Pump Turbine Control (2 sheets) 7.3-16 2 of 2 441270-1 7.3-17 1 of 2 437583-1 Schematic Diagram - Motor-Driven Auxiliary Feedwater Pumps (2 sheets) 7.3-17 2 of 2 441302-1 7.3-18 1 of 4 437584-1 Schematic Diagram - Auxiliary Feedwater Pumps Turbine Control (4 Sheets) 7.3-18 2 of 4 455060-1 7.3-18 3 of 4 441303-1 7.3-18 4 of 4 455097-1 7.3-19 1 of 2 437585-1 Schematic Diagram - Feedwater Motor-Operated Isolation Valves (2 sheets) 7.3-19 2 of 2 441304-1 7.3-20 1 of 2 477846-1 Schematic Diagram - Reactor Coolant Pump (2 sheets) 7.3-20 2 of 2 441305-1 7.3-21 1 of 4 437587-1 Schematic Diagram - Reactor Coolant Motor-Operated Valves and Reactor Coolant System Solenoid Valves (4 Sheets) 7.3-21 2 of 4 437609-1 7.3-21 3 of 4 441306-1 7.3-21 4 of 4 441328-1 7.3-22 1 of 2 437588-1 Schematic Diagram - Safety Injection System Solenoid Valves (2 sheets) 7.3-22 2 of 2 441316-1 7.3-23 1 of 2 437589-1 Schematic Diagram - Safety Injection Pumps (2 sheets) 7.3-23 2 of 2 441315-1 7.3-24 1 of 2 437590-1 Schematic Diagram - Containment Spray Pumps (2 sheets) 7.3-24 2 of 2 441307-1 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 21 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 7.3-25 1 of 2 437591-1 Schematic Diagram - Residual Heat Removal Pumps (2 sheets) 7.3-25 2 of 2 441309-1 7.3-26 1 of 2 437592-1 Schematic Diagram - Residual Heat Removal Flow Control Valves (2 sheets) 7.3-26 2 of 2 441310-1 7.3-27 1 of 2 437593-1 Schematic Diagram - Component Cooling Water Pumps (2 sheets) 7.3-27 2 of 2 441311-1 7.3-28 1 of 2 437594-1 Schematic Diagram - Auxiliary Saltwater Pumps (2 sheets) 7.3-28 2 of 2 441287-1 7.3-29 1 of 2 437595-1 Schematic Diagram - Charging Pumps (2 sheets) 7.3-29 2 of 2 441312-1 7.3-30 1 of 8 437596-1 Schematic Diagram - Chemical and Volume Control System (8 Sheets) 7.3-30 2 of 8 437597-1 7.3-30 3 of 8 437598-1 7.3-30 4 of 8 437599-1 7.3-30 5 of 8 441320-1 7.3-30 6 of 8 441321-1 7.3-30 7 of 8 441322-1 7.3-30 8 of 8 477316-1 7.3-31 1 of 4 437600-1 Schematic Diagram - Containment Fan Coolers (4 sheets) 7.3-31 2 of 4 437600-2 7.3-31 3 of 4 441313-1 7.3-31 4 of 4 441313-2 7.3-32 1 of 2 437604-1 Schematic Diagram - Containment Spray System Motor-Operated Valves (2 sheets) 7.3-32 2 of 2 441308-1 7.3-33 1 of 5 (U1) 437605-1 Schematic Diagram - Safety Injection System Motor-Operated Valves (5 Sheets) 7.3-33 2 of 5 (U1) 437606-1 7.3-33 3 of 5 (U2) 441317-1 7.3-33 4 of 5 (U2) 441318-1 7.3-33 5 of 5 (U2) 441318-2 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 22 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 7.3-34 1 of 3 (U1) 437607-1 Schematic Diagram - Chemical and Volume Control System Motor-Operated Valves. (2 sheets) 7.3-34 2 of 3 (U2) 441324-1 7.3-34 3 of 3 (U2) 441324-2 7.3-35 1 of 2 437608-1 Schematic Diagram - Component Cooling Water System Motor-Operated Valves (2 sheets) 7.3-35 2 of 2 441325-1 7.3-36 1 of 2 437610-1 Schematic Diagram - Reactor Trip Breakers (2 sheets) 7.3-36 2 of 2 441489-1 7.3-37 437630-1 Schematic Diagram - Fire Pumps 7.3-38 1 of 2 437631-1 Schematic Diagram - Containment Purge System (2 sheets) 7.3-38 2 of 2 441490-1 7.3-39 437632-1 Schematic Diagram - Plant Air Compressors 7.3-40 1 of 4 437634-1 Schematic Diagram - Control Rod Drive Motor Generator Set (4 Sheets) 7.3-40 2 of 4 437603-1 7.3-40 3 of 4 441488-1 7.3-40 4 of 4 441487-1 7.3-41 437657-1 Schematic Diagram - Diesel Fuel Transfer Pumps 7.3-42 1 of 2 437679-1 Schematic Diagram - Main Steam Isolation Valves (2 sheets) 7.3-42 2 of 2 441296-1 7.3-43 1 of 2 437680-1 Schematic Diagram - Sampling System Solenoid Valves (2 sheets) 7.3-43 2 of 2 441329-1 7.3-44 1 of 2 437681-1 Schematic Diagram - Component Cooling Water Solenoid Valves (2 sheets) 7.3-44 2 of 2 441330-1 7.3-45 1 of 4 437682-1 Schematic Diagram - Chemical and Volume Control System Solenoid Valves (4 Sheets) 7.3-45 2 of 4 437683-1 7.3-45 3 of 4 441326-1 7.3-45 4 of 4 441327-1 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 23 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 7.3-46 1 of 2 437684-1 Schematic Diagram - Liquid Radwaste Solenoid Valves (2 sheets) 7.3-46 2 of 2 441319-1 7.3-47 1 of 2 437685-1 Schematic Diagram - Steam Generator Blowdown Solenoid Valves (2 sheets) 7.3-47 2 of 2 441461-1 7.3-48 1 of 4 437557-1 Schematic Diagram - Generator Control (4 Sheets) 7.3-48 2 of 4 437558-1 7.3-48 3 of 4 441245-1 7.3-48 4 of 4 441246-1 7.3-49 1 of 2 437701-1 Schematic Diagram - Permissive and Bypass Lights (2 sheets) 7.3-49 2 of 2 441369-1 7.3-50 1 of 3 445650-1 Separ ation and Color Code Instrumentation and Control - Engineered Safety Features (3 Sheets) 7.3-50 2A of 3 442561-1 7.3-50 2 of 3 445651-1 7.3-52 1 of 4 057673-1 Containment Electrical Penetrations, Cable Trays, and Supports (4 Sheets) 7.3-52 2 of 4 501445-1 7.3-52 3 of 4 500603-1 7.3-52 4 of 4 500793-1 7.6-1 1 of 6 437547-1 Instrumentation and Control Power Supply (6 Sheets) 7.6-1 2 of 6 445290-1 7.6-1 3 of 6 445291-1 7.6-1 4 of 6 441241-1 7.6-1 5 of 6 445390-1 7.6-1 6 of 6 445391-1 7.7-6 495860-1 Unit 1: Functional Logic Diagram, Digital Feedwater Control System, FW Flow Controller & Cv Demand 7.7-6 495890-1 Unit 2: Functional Logic Diagram, Digital Feedwater Control System, FW Flow Controller
& Cv Demand DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 24 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 7.7-7 495853-1 Unit 1: Functional Logic Diagram, Digital Feedwater Control System, Feedwater Control & Isolation 7.7-7 495883-1 Unit 2: Functional Logic Diagram, Digital Feedwater Control System, Feedwater Control
& Isolation 7.7-16 507613-1 Arrangement of Control Room 7.7-17 504479-1 Location of Control Console and Main Control Board 7.7-18 521120-1 Arrangement of Control Console Nuclear Instrumentation System (CC1), Primary Plant Control (CC2), and Secondary Plant Control (CC3) - Unit 1 7.7-19 521130-1 Arrangement of Control Console Nuclear Instrumentation System (CC1), Primary Plant Control (CC2), and Secondary Plant Control (CC3) - Unit 2 7.7-20 521121-1 Arrangement of Main Control Board - Engineered Safety Systems (VB1) - Unit 1 7.7-21 521131-1 Arrangement of Main Control Board - Engineered Safety Systems (VB1) - Unit 2 7.7-22 521122-1 Arrangement of Main Control Board - Primary Plant Systems (VB2) - Unit 1 7.7-23 521132-1 Arrangement of Main Control Board - Primary Plant Systems (VB2) - Unit 2 7.7-24 521123-1 Arrangement of Main Control Board - Steam and Turbine (VB3) - Unit 1 7.7-25 521133-1 Arrangement of Main Control Board - Steam and Turbine (VB3) - Unit 2 7.7-26 521124-1 Arrangement of Main Control Board - Auxiliary Equipment and Diesel VB4) - Unit 1 7.7-27 521134-1 Arrangement of Main Control Board - Auxiliary Equipment and Diesel VB4) - Unit 2 7.7-28 521125-1 Arrangement of Main Control Board - Station Electric (VB5) - Unit 1 7.7-29 521135-1 Arrangement of Main Control Board - Station Electric (VB5) - Unit 2 7.7-30 1 of 3 (U2) 480237-1 Arrangement of Hot Shutdown Remote Control Panel (3 sheets) 7.7-30 2 of 3 (U1) 491716-1 7.7-30 3 of 3 (U2) 494122-1 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 25 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 7.7-31 330557-1 Arrangement of Auxiliary Building Control Panel 8.1-1 502110-1 Plant Single Line Diagram 8.2-3 57483-1 General Arrangement 230-kV and 500-kV Switchyard 8.2-6 500804-1 Arrangement of 12-kV Startup Transformers 8.3-1 1 of 2 437529-1 Single Line Meter and Relay Diagram -
Generator, Main, and Auxiliary Transformers, and Excitation (2 sheets) 8.3-1 2 of 2 441226-1 8.3-2 1 of 2 437531-1 Single Line Meter and Relay Diagram kV System (2 sheets) 8.3-2 2 of 2 441227-1 8.3-3 1 of 2 437532-1 Single Line Meter and Relay Diagram kV System (2 sheets) 8.3-3 2 of 2 441228-1 8.3-4 1 of 3 437533-1 Single Line Meter and Relay Diagram kV System (Vital Bus) (3 sheets) 8.3-4 2 of 3 441229-1 8.3-4 3 of 3 441230-1 8.3-5 437530-1 Single Line Meter and Relay Diagram kV Startup System 8.3-6 1 of 2 437916-1 Single Line Meter and Relay Diagram - 480-V System Bus Section F (Vital Bus) (2 sheets) 8.3-6 2 of 2 441237-1 8.3-7 1 of 2 437542-1 Single Line Meter and Relay Diagram - 480-V System Bus Section G (Vital Bus) (2 sheets) 8.3-7 2 of 2 441238-1 8.3-8 1 of 2 437543-1 Single Line Meter and Relay Diagram - 480-V System Bus Section H (Vital Bus) (2 sheets) 8.3-8 2 of 2 441239-1 8.3-9 1 of 2 437625-1 Schematic Diagram kV Bus Section F Automatic Transfer (2 sheets) 8.3-9 2 of 2 441352-1 8.3-10 1 of 2 437626-1 Schematic Diagram kV Bus Section G Automatic Transfer (2 sheets) 8.3-10 2 of 2 441353-1 8.3-11 1 of 2 437627-1 Schematic Diagram kV Bus Section H Automatic Transfer (2 sheets) 8.3-11 2 of 2 441354-1 DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 26 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 8.3-12 1 of 11 437579-1 Schematic Diagram kV Diesel Generators Controls (11 Sheets) 8.3-12 2 of 11 437580-1 8.3-12 3 of 11 437667-1 8.3-12 4 of 11 437668-1 8.3-12 5 of 11 441357-1 8.3-12 6 of 11 441358-1 8.3-12 7 of 11 496277-1 8.3-12 8 of 11 496278-1 8.3-12 9 of 11 496279-1 8.3-12 10 of11 496280-1 8.3-12 11 of 11 496281-1 8.3-13 1 of 7 437665-1 Schematic Diagram kV Diesel Generators and Associated Circuit Breakers (7 Sheets) 8.3-13 2 of 7 437676-1 8.3-13 3 of 7 437666-1 8.3-13 4 of 7 441355-1 8.3-13 5 of 7 441356-1 8.3-13 6 of 7 496275-1 8.3-13 7 of 7 496276-1 8.3-14 1 of 3 437674-1 Schematic Diagram kV Diesel Generators Auxiliary Motors (3 sheets) 8.3-14 2 of 3 441359-1 8.3-14 3 of 3 496282-1 8.3-16 1 of 6 458863-1 Logic Diagram - Automatic Transfer 4-kV buses F, G, and H (6 Sheets) 8.3-16 2 of 6 458864-1 8.3-16 3 of 6 458865-1 8.3-16 4 of 6 441286-1 8.3-16 5 of 6 441297-1 8.3-16 6 of 6 441337-1 8.3-17 1 of 4 437546-1 Cla ss 1E 125-Vdc System (4 Sheets) 8.3-17 2 of 4 445076-1 8.3-17 3 of 4 445075-1 8.3-17 4 of 4 441240-1 8.3-18 1 of 2 455065-1 Normal (Non-Class 1E) 125-V and 250-Vdc System (2 sheets)
DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 27 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 8.3-18 2 of 2 445295-1 8.3-19 1 of 2 437545-1 Pressurizer Heaters, Single Line Diagram (2 sheets) 8.3-19 2 of 2 441218-1 8.3-20 1 of 2 437614-1 Schematic Diagram Potential and Synchronizing 4160-Volt System (Vital Bus) (2 sheets) 8.3-20 2 of 2 441340-1 9.4-1 511157-1 Air Conditioning, Heating, Cooling, and Ventilation Systems - Control Room 9.4-2 1 of 2 59316-1 Air Conditioning, Cooling, and Ventilation Systems - Auxiliary Building (2 sheets) 9.4-2 2 of 2 501365-1 9.4-3 59317-1 Ventilation Flow Diagram Containment Fuel Handling Fan Rooms (Unit 1) 9.4-3A 501366-1 Ventilation Flow Diagram Containment Fuel Handling Fan Rooms (Unit 2) 9.4-8 516103-1 Ventilation System - Inverter Rooms and 480 V Switchgear Room in Auxiliary Building 9.4-10 512904-1 Ventilation Systems - Technical Support Center and Post-Accident Sampling Room 9.5-8 508845-1 Diesel Fuel Oil Transfer Pump Vaults 9.5-9 438165-1 Diesel Generator Fuel Oil Piping 9.5-10 1 of 4 500002-1 Dies el Generator Arrangement Plan (4 sheets) 9.5-10 2 of 4 500852-1 9.5-10 3 of 4 498992-1 9.5-10 4 of 4 498993-1 9.5-11 1 of 2 500003-1 Di esel Generator Arrangement Sections (2 sheets) 9.5-11 2 of 2 500853-1 9.5-12 663082-2 Diesel Engine Generator (Typical) 9.5F-1 515562-1 Fire Areas, Turbine Building Elevation 85 ft 9.5F-2 515563-1 Fire Areas, Turbine Building Elevation 104 ft 9.5F-3 515564-1 Fire Areas, Turbine Building Elevation 119 ft 9.5F-4 515565-1 Fire Areas, Turbine Building Elevation 140 ft DCPP UNITS 1 &
2 FSAR UPDATE TABLE 1.6-1 Sheet 28 of 28 Revision 23 December 2016 Figure Sheet Drawing Description 9.5F-5 515566-1 Fire Areas, Auxiliary Building Elevation 54 ft and 64 ft 9.5F-6 515567-1 Fire Areas, Auxiliary Building Elevation 75 ft 9.5F-7 515568-1 Fire Areas, Auxiliary Building + Containment, Elevation 85 ft 9.5F-8 515569-1 Fire Areas, Auxiliary Building + Containment +
Fuel Handling Elevation 100 ft 9.5F-9 515570-1 Fire Areas, Auxiliary Building + Containment +
Fuel Handling Elevation 115 ft 9.5F-10 515571-1 Fire Areas, Auxiliary Building + Containment +
Fuel Handling Elevation 140 ft 9.5F-11 515572-1 Fire Areas, Auxiliary Building Elevation 125'-8", 127'-4" and 163'-4" 9.5F-12 515573-1 Fire Areas, Turbine Building Elevation 85 ft 9.5F-13 515574-1 Fire Areas, Turbine Building Elevation 104 ft 9.5F-14 515575-1 Fire Areas, Turbine Building Elevation 119 ft 9.5F-15 515576-1 Fire Areas, Turbine Building Elevation 140 ft 9.5F-16 515577-1 Fire Areas, Auxiliary Building + Containment + Fuel Handling Elevation 85 ft and 100 ft 9.5F-17 515578-1 Fire Areas, Auxiliary Building + Containment + Fuel Handling Elevation 115 ft and 140 ft 9.5F-18 515580-1 Fire Areas, Intake Structure 9.5F-19 515579-1 Fire Areas, Buttress Area 10.1-1 6021770-30 Unit 2: Heat Balance Diagram - Maximum Calculated - Post LP Retrofit 10.1-2 6021770-22 Unit 2: Heat Balance Diagram - 100% RTO -
Post LP Retrofit 10.1-5 6021770-19 Unit 1: Heat Balance Diagram - Maximum Calculated - Post LP Retrofit 10.1-6 6021770-5 Unit 1: Heat Balance Diagram - 100% RTO -
Post LP Retrofit 11.5-5 502699-1 Solid Radwaste Storage Building