ML21109A087
Text
PBAPS UFSAR SECTION 1.0 - INTRODUCTION AND
SUMMARY
TABLE OF CONTENTS SECTION TITLE 1.1 PROJECT IDENTIFICATION 1.1.1 Identification and Qualifications of Contractors 1.1.1.1 Applicant 1.1.1.2 Engineer-Constructor 1.1.1.3 Nuclear Steam Supply System Supplier 1.1.1.4 Turbine-Generator Supplier 1.1.1.5 Consultants During Design and Construction 1.1.1.6 Contractors and Consultants for Plant Modifications 1.1.1.7 Updated FSAR Contractor 1.2 DEFINITIONS 1.3 METHODS OF TECHNICAL PRESENTATION 1.3.1 Purpose 1.3.2 Radioactive Material Barrier Concept 1.3.3 Organization of Contents 1.3.4 Format Organization of Subsections 1.3.5 Power Level Basis for Analysis of Abnormal Operational Transients and Accidents 1.4 CLASSIFICATION OF BWR SYSTEMS, CRITERIA, AND REQUIREMENTS FOR SAFETY EVALUATION 1.4.1 Introduction 1.4.2 Classification Basis 1.4.3 Use of the Classification Plan 1.5 PRINCIPAL DESIGN CRITERIA 1.5.1 Principal Design Criteria, Classification- By-Classification 1.5.1.1 General Criteria 1.5.1.2 Power Generation Design Criteria, Type PG-1 (Planned Operation) 1.5.1.3 Power Generation Design Criteria, Type PG-2 (Abnormal Operational Transients) 1.5.1.4 Nuclear Safety Design Criteria, Type S-1 (Planned Operation) 1.5.1.5 Nuclear Safety Design Criteria, Type S-2 Abnormal Operational Transients) 1.5.1.6 Nuclear Safety Design Criteria, Type S-3 (Accidents) 1.5.1.7 Nuclear Safety Design Criteria, Type S-4 (Special Event) 1.5.1.8 Nuclear Safety Design Criteria, Type S-5 (Special Event)
CHAPTER 01 1-i REV. 28, APRIL 2020
PBAPS UFSAR TABLE OF CONTENTS (cont'd)
SECTION TITLE 1.5.2 Principal Design Criteria, System-By-System 1.5.2.1 General Criteria 1.5.2.2 Nuclear System Criteria 1.5.2.3 Power Conversion System Criteria 1.5.2.4 Electrical Power System Criteria 1.5.2.5 Radioactive Waste Disposal Criteria 1.5.2.6 Nuclear Safety Systems and Engineered Safeguards Criteria 1.5.2.6.1 General 1.5.2.6.2 Containment and Isolation Criteria 1.5.2.6.3 Core Standby Cooling Criteria 1.5.2.6.4 Standby Power Criteria 1.5.2.7 Reactivity Control Criteria 1.5.2.8 Process Control Systems Criteria 1.5.2.8.1 Nuclear System Process Control Criteria 1.5.2.8.2 Power Conversion Systems Process Control Criteria 1.5.2.8.3 Electrical Power System Process Control Criteria 1.5.2.9 Auxiliary Systems Criteria 1.5.2.10 Shielding and Access Control Criteria 1.5.2.11 Structural Loading Criteria 1.6 PLANT DESCRIPTION 1.6.1 General 1.6.1.1 Site and Environs 1.6.1.1.1 Location and Size of Site 1.6.1.1.2 Site Ownership 1.6.1.1.3 Activities at the Site 1.6.1.1.4 Access to Site 1.6.1.1.5 Description of the Environs 1.6.1.1.6 Geology 1.6.1.1.7 Seismology 1.6.1.1.8 Hydrology 1.6.1.1.9 Meteorology 1.6.1.1.10 Design Bases Dependent Upon Site and Environs 1.6.1.2 Facility Arrangement 1.6.1.3 Nuclear System 1.6.1.3.1 Reactor Core and Control Rods 1.6.1.3.2 Reactor Vessel and Internals 1.6.1.3.3 Reactor Recirculation System 1.6.1.3.4 Residual Heat Removal System 1.6.1.3.5 Reactor Water Cleanup System 1.6.1.4 Power Conversion System 1.6.1.4.1 Turbine-Generator CHAPTER 01 1-ii REV. 28, APRIL 2020
PBAPS UFSAR TABLE OF CONTENTS (cont'd)
SECTION TITLE 1.6.1.4.2 Turbine Bypass System 1.6.1.4.3 Main Condenser 1.6.1.4.4 Main Condenser Air Ejector and Turbine Steam Sealing Systems 1.6.1.4.5 Circulating Water and Cooling Tower System 1.6.1.4.6 Condensate Filter-Demineralizer System 1.6.1.4.7 Condensate and Feedwater System 1.6.1.5 Electrical Power System 1.6.1.6 Radioactive Waste Systems 1.6.1.6.1 Liquid Radwaste System 1.6.1.6.2 Solid Radwaste System 1.6.1.6.3 Gaseous Radwaste System 1.6.1.6.3B DELETED 1.6.2 Nuclear Safety Systems and Engineered Safeguards 1.6.2.1 Reactor Protection System 1.6.2.2 Neutron Monitoring System 1.6.2.3 Control Rod Drive System 1.6.2.4 Nuclear System Pressure Relief System 1.6.2.5 Reactor Core Isolation Cooling System 1.6.2.6 Primary Containment 1.6.2.7 Primary Containment and Reactor Vessel Isolation Control System 1.6.2.8 Secondary Containment 1.6.2.9 Main Steam Line Isolation Valves 1.6.2.10 Main Steam Line Flow Restrictors 1.6.2.11 Core Standby Cooling Systems 1.6.2.12 Residual Heat Removal System (Containment Cooling) 1.6.2.13 Control Rod Velocity Limiter 1.6.2.14 Control Rod Drive Housing Supports 1.6.2.15 Standby Gas Treatment System 1.6.2.16 Standby ac Power Supply 1.6.2.17 dc Power Supply 1.6.2.18 High-Pressure Service Water System 1.6.2.19 Emergency Service Water System 1.6.2.20 Main Steam Line Radiation Monitoring System 1.6.2.21 Ventilation Radiation Monitoring System 1.6.2.22 Standby Liquid Control System 1.6.3 Special Safety Systems 1.6.3.1 Standby Liquid Control System 1.6.3.2 Shutdown Capability Outside the Control Room 1.6.3.3 Emergency Heat Sink 1.6.3.4 Alternate Rod Insertion 1.6.4 Process Control and Instrumentation CHAPTER 01 1-iii REV. 28, APRIL 2020
PBAPS UFSAR TABLE OF CONTENTS (cont'd)
SECTION TITLE 1.6.4.1 Nuclear System Process Control and Instrumentation 1.6.4.1.1 Reactor Manual Control System 1.6.4.1.2 Recirculation Flow Control System 1.6.4.1.3 Neutron Monitoring System 1.6.4.1.4 Refueling Interlocks 1.6.4.1.5 Reactor Vessel Instrumentation 1.6.4.1.6 Process Computer System 1.6.4.2 Power Conversion Systems Process Control and Instrumentation 1.6.4.2.1 Pressure Regulator and Turbine Control 1.6.4.2.2 Feedwater System Control 1.6.4.3 Electrical Power System Control 1.6.4.4 Radiation Monitoring 1.6.4.4.1 Process Radiation Monitoring 1.6.4.4.2 Area Radiation Monitoring 1.6.4.4.3 Site Environs Radiation Monitors 1.6.4.4.4 Liquid Radwaste System Control 1.6.4.4.5 Solid Radwaste Control 1.6.4.4.6 Gaseous Radwaste System Control 1.6.4.4.6B DELETED 1.6.5 Auxiliary Systems 1.6.5.1 Normal Auxiliary ac Power 1.6.5.2 Reactor Building Cooling Water System 1.6.5.3 Turbine Building Cooling Water System 1.6.5.4 Service Water System 1.6.5.5 Fire Protection System 1.6.5.6 Heating, Ventilation, and Air Conditioning Systems 1.6.5.7 New and Spent Fuel Storage 1.6.5.8 Fuel Pool Cooling and Cleanup System 1.6.5.9 Service and Instrument Air System 1.6.5.10 Makeup Water System 1.6.5.11 Potable and Sanitary Water Systems 1.6.5.12 Equipment and Floor Drainage System 1.6.5.13 Process Sampling System 1.6.5.14 Station Communications System 1.6.6 Shielding 1.6.7 Loading Criteria 1.7 COMPARISON OF PRINCIPAL DESIGN CHARACTERISTICS 1.7.1 Nuclear System Design Characteristics 1.7.2 Power Conversion Systems Design Characteristics 1.7.3 Electrical Power Systems Design Characteristics 1.7.4 Containment Design Characteristics CHAPTER 01 1-iv REV. 28, APRIL 2020
PBAPS UFSAR TABLE OF CONTENTS (cont'd)
SECTION TITLE 1.7.5 Structural Design Characteristics 1.8
SUMMARY
OF RADIATION EFFECTS 1.8.1 Normal Operation 1.8.2 Abnormal Operational Transients 1.8.3 Accidents 1.8.4 Interaction With Unit 1 1.8.5 Independent Spent Fuel Storage Installation 1.9 PLANT MANAGEMENT 1.9.1 Organizational Structure 1.9.2 Operator Training 1.9.3 Safety Responsibilities 1.9.4 Emergency Plans 1.9.5 Cooperation With Other Agencies 1.10 QUALITY ASSURANCE PROGRAM 1.11 STATION RESEARCH DEVELOPMENT AND FURTHER INFORMATION; REQUIREMENTS AND RESOLUTIONS
SUMMARY
1.11.1 General 1.12 EXTENDED POWER UPRATE COMPUTER CODES/METHODOLOGIES 1.12.1 General 1.13 MELLLA+ COMPUTER CODES/METHODOLOGIES 1.13.1 General 1.14 MEASUREMENT UNCERTAINTY RECAPTURE CODES/METHODOLOGIES 1.14.1 General 1.15 RISK INFORMED CATEGORIZATION AND TREATMENT 1.15.1 Introduction 1.15.2 Scope 1.15.3 SSC Categorization 1.15.4 Alternative Treatment 1.15.5 Periodic Reviews 1.15.6 References CHAPTER 01 1-v REV. 28, APRIL 2020
PBAPS UFSAR SECTION 1.0 - INTRODUCTION AND
SUMMARY
LIST OF TABLES TABLE TITLE 1.4.1 BWR Safety Engineering Concept for Classification of BWR Systems, Criteria, and Requirements for Safety Evaluation 1.4.2 Classification of BWR Systems, Criteria, and Requirements for Safety Evaluation 1.5.1 DELETED 1.7.1 Comparison of Nuclear System Design Characteristics 1.7.2 Comparison of Power Conversion System Design Characteristics 1.7.3 Comparison of Electrical Power Systems Design Characteristics 1.7.4 Comparison of Containment Design Characteristics 1.7.5 Comparison of Structural Design Characteristics 1.8.1 DELETED 1.11.1 Peach Bottom Atomic Power Station Units 2 and 3 Topical Reports Submitted to the AEC in Support of Docket 1.11.2 AEC-ACRS Concerns - Resolutions 1.11.3 AEC-Staff Concerns - Resolutions 1.11.4 AEC-ACRS Concerns on Other Dockets - Capability for Resolution 1.11.5 AEC-Staff Concerns on Other Dockets - Capability for Resolution 1.12.1 Power Computer Codes Used for Extended Power Uprate Analyses 1.13.1 Computer Codes Used for MELLLA+ Analyses 1.14.1 Computer Codes Used for MUR Analyses CHAPTER 01 1-vi REV. 28, APRIL 2020
PBAPS UFSAR SECTION 1.0 - INTRODUCTION AND
SUMMARY
LIST OF FIGURES FIGURE TITLE 1.2.1 Relationship Between Safety Action and Protective Action 1.2.2 Relationship Between Protective Function and Protective Action 1.2.3 Relationship Between Different Types of Systems, Actions, and Objectives 1.3.1 Deleted 1.3.1 Deleted 1.6.1 Flow Diagram - General Plant Systems, Unit 2 Sheet 1 of 2 1.6.1 Flow Diagram - General Plant Systems, Unit 3 Sheet 2 of 2 1.6.2 Reactor Heat Balance - Rated Power 1.6.2A Deleted 1.6.2b Deleted 1.6.2c Deleted 1.6.3 Turbine-Generator Heat Balance - Rated Power Sheet 1 of 1 CHAPTER 01 1-vii REV. 28, APRIL 2020