THIS VERSION OF DIABLO CANYON POWER PLANT FINAL SAFETY ANALYSIS REPORT UPDATE (UFSAR) CONTAINS SECTIONS 2.5, 3.7 AND 3.10 OF THE LICENSEE’S REVISION 21, ISSUED SEPTEMBER 2013, WITH CERTAIN REDACTIONS OF SENSITIVE INFORMATION BY STAFF OF THE NUCLEAR REGULATORY COMMISSION (nrc) TO ALLOW RELEASE TO THE PUBLIC. THE REDACTIONS ARE MADE UNDER 10 CFR 2.390(d)(1). THE MATERIAL INCLUDED WITH IS CLASSIFIED AS PUBLICLY AVAILABLE INFORMATION. AS OF SEPTEMBER 2014, THIS IS THE LATEST UFSAR REVISION SUBMITTED TO NRC. THE REDACTIONS WERE MADE DUE TO MEETING THE NRC’S CRITERIA ON SENSITIVE INFORMATION, AS SPECIFIED IN SECY-04-0191, “WITHHOLDING SESITIVE UNCLASSIFIED INFORMATION CONCERNING NUCLEAR POWER REACTORS FROM PUBLIC DISCLOSURE,” DATED OCTOBER 19, 2004, ADAMS ACCESSION NO. ML042310663, AS MODIFIED BY THE NRC COMMISSIONERS STAFF REQUIREMENTS MEMORANDUM ON SECY-04-0191, DATED NOVEMBER 9, 2004, ADAMS ACCESSION NO. 043140175. Diablo Canyon Power Plant Units 1 and 2 Final Safety Analysis Report Update Revision 21 September 2013 Docket No. 50-275 Docket No. 50-323 DIABLO CANYON POWER PLANT UNITS 1 AND 2 FSAR UPDATE CONTENTS 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 Design Class I Structures 3.9 Mechanical Systems and Components 3.10 Seismic Design of 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 i Revision 21 September 2013 DIABLO CANYON POWER PLANT UNITS 1 AND 2 FSAR UPDATE CONTENTS 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 Vessel and Appurtenances 5.5 Component and Subsystem Design 5.6 Instrumentation Requirements Tables for Chapter 5 Figures for Chapter 5 Appendices 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 ii Revision 21 September 2013 DIABLO CANYON POWER PLANT UNITS 1 AND 2 FSAR UPDATE CONTENTS 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 11.1 Source Terms 11.2 Liquid Waste System 11.3 Gaseous Waste System 11.4 Process and Effluent Radiological Monitoring System 11.5 Solid Waste System iii Revision 21 September 2013 DIABLO CANYON POWER PLANT UNITS 1 AND 2 FSAR UPDATE CONTENTS Chapter 11 (continued) 11.6 Offsite Radiological Monitoring Program Tables for Chapter 11 Figures for Chapter 11 Chapter 12 - RADIATION PROTECTION 12.1 Shielding 12.2 Ventilation 12.3 Health Physics 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 iv Revision 21 September 2013 DIABLO CANYON POWER PLANT UNITS 1 AND 2 FSAR UPDATE CONTENTS Chapter 15 - ACCIDENT ANALYSES 15.1 Condition I - Normal Operation and Operational Transients 15.2 Condition II - Faults of Moderate Frequency 15.3 Condition III - Infrequent Faults 15.4 Condition IV - Limiting Faults 15.5 Environmental 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 17.1 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 Tables for Chapter 17 Figures for Chapter 17 v Revision 21 September 2013 DCPP UNITS 1 & 2 FSAR UPDATE 2.5 GEOLOGY AND SEISMOLOGY This section presents the findings of the regional and site-specific geologic and seismologic investigations of the Diablo Canyon Power Plant (DCPP) site. Information presented is in compliance with the criteria in Appendix A of 10 CFR Part 100, as described below, and meets the format and content recommendations of Regulatory Guide 1.70, Revision 1 (Reference 39). Because the development of the seismic inputs for DCPP predates the issuance of 10 CFR Part 100, Appendix A, "Seismic and Geologic Siting Criteria for Nuclear Power Plants," the DCPP earthquakes are plant specific. To capture the historical progress of the geotechnical and seismological investigations associated with the DCPP site, information pertaining to the following three time periods is described herein: (1) Original Design Phase: investigations performed in support of the Preliminary Safety Analysis Report, prior to the issuance of the Unit 1 construction permit (1967), through the early stages of the construction of Unit 1 (1971). The Design Earthquake and Double Design Earthquake ground motions are associated with this phase. These earthquakes are similar to the regulatory ground motion level that the NRC subsequently developed in 10 CFR Part 100 Appendix A as the "Operating Basis Earthquake (OBE)" ground motion and the "Safe Shutdown Earthquake (SSE)" ground motion, respectively. (2) Hosgri Evaluation Phase: investigations performed in response to the identification of the offshore Hosgri fault zone (1971) through the issuance of the Unit 1 operating license (1984). The 1977 Hosgri Earthquake ground motions are associated with this phase. The Hosgri Evaluation Phase does not affect or change the investigations and conclusions of the Original Design Phase. (3) Long Term Seismic Program (LTSP) Evaluation Phase: investigations performed in response to the License Condition Item No. 2.C.(7) of the Unit 1 operating license (1984) through the removal of the License Condition (1991), including current on-going investigations. The 1991 L TSP ground motion is associated with this phase. The LTSP Evaluation Phase does not affect or change the investigations and conclusions of either the Original Design Phase or the Hosgri Evaluation Phase. Overview Locations of earthquake epicenters within 200 miles of the plant site, and faults and earthquake epicenters within 75 miles of the plant site for either magnitudes or intensities, respectively, are shown in Figures 2.5-2, 2.5-3, and 2.5-4 (through 1972). A geologic and tectonic map of the region surrounding the site is shown in Figure 2.5-5, 2.5-1 Revision 21 September 2013 DCPP UNITS 1 & 2 FSAR UPDATE and detailed information about site geology is presented in Figures 2.5-8 through 2.5-16. Geology and seismology are discussed in detail in Sections 2.5.2 through 2.5.5. Additional information on site geology is contained in References 1 and 2. Detailed supporting data pertaining to this section are presented in Appendices 2.5A, 2.5B, 2.5C, and 2.5D of Reference 27 in Section 2.3. Geologic and seismic information from investigations that responded to Nuclear Regulatory Commission (NRC) licensing review questions are presented Appendices 2.5E and 2.5F of the same reference. A brief synopsis of the information presented in Reference 27 (Section 2.3) is given below.