AP1000 European 1. Introduction and General Description of the Plant Design Control Document

Transcription

1 CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF THE PLANT 1.1 Introduction This Design Control Document (DCD) for the Westinghouse AP1000 simplified passive advanced light water reactor plant is incorporated by reference into the Design Certification Rule for the AP1000 design (Section II.A) of Appendix D to 10 CFR Part 52. The DCD is also submitted to the NRC for review and approval of an application for an amendment to the Design Certification Rule for the AP Plant Location The AP1000 is a standardized plant that is to be placed on a site with parameters described in Chapter 2, Site Characteristics. The site parameters relate to the seismology, hydrology, meteorology, geology, heat sink, and other site-related aspects Containment Type The containment building is a freestanding, cylindrical, steel containment vessel with elliptical upper and lower heads. It is surrounded by a seismic Category I reinforced concrete shield building. The containment vessel is an integral part of the passive containment cooling system. The vessel provides the safety-related interface with the ultimate heat sink, which is the surrounding atmosphere. Westinghouse is responsible, along with their contractor team members, for the design of the containment Reactor Type The nuclear steam supply system (NSSS) for the AP1000 is a Westinghouse-designed pressurized water reactor Power Output Schedule The plant's net producible electrical power to the grid is at least 1000 MWe, with a core power rating of 3400 MWt. In some safety evaluations a power level higher than the rated power level is employed. The scheduled completion date and estimated commercial operation date of nuclear power plants referencing the AP1000 design certification are provided as discussed in subsection EPS-GW-GL Revision 1

2 1.1.6 Format and Content Regulatory Guide 1.70 To the extent practical, the AP1000 DCD has used as a guide the format and content recommendations of Regulatory Guide 1.70, Revision 3, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants - LWR Edition, November The DCD generally uses the same chapter, section, subsection, and paragraph headings used in the standard format. Where appropriate, the DCD is subdivided beyond the extent of the standard format to provide additional information specifically required for that area. Similarly, some of the passive features of the AP1000 require modification of the standard format and content either in terms of placement or type of material presented Standard Review Plan The technical guidance provided in NUREG-0800, is followed in the preparation of the AP1000 DCD. Standard Review Plan conformance is also determined in accordance with 10 CFR to identify the deviations of the AP1000 DCD from the Standard Review Plan. See subsection for additional details on Standard Review Plan conformance Text, Tables and Figures AP1000 DCD tables of data are identified by the section or subsection number followed by a sequential number (for example, Table is the fifth table of Section 3.3). Tables are located at the end of the section immediately following the text. Drawings, pictures, sketches, curves, graphs, plots, and engineering diagrams are identified as figures and are numbered sequentially by section or subsection similar to tables, and follow at the end of the applicable section or subsection Numbering of Pages Text pages are numbered sequentially within each section or subsection Proprietary Information The AP1000 DCD contains no proprietary information DCD Acronyms Table provides a list of acronyms used in the AP1000 DCD. Acronyms for systems are defined in the section in which they are used. Other acronyms may be defined in the section in which they are used. Table provides a list of AP1000 system designators Combined License Information Combined License applicants referencing the AP1000 certified design will provide the construction and startup schedule information. EPS-GW-GL Revision 1

3 Table (Sheet 1 of 4) ac ACI ACRS ADS AISC AISI ALARA ALWR AMCA ANS ANL ANSI API ARI ASCE ASHRAE ASME ASTM ATWS AWS BEACON BOL BOP BTP CFR CHF CMAA CMT COL CRD CRDM CSA CVS DAC dc DBA DBE DCD Alternating Current American Concrete Institute Advisory Committee on Reactor Safeguards Automatic Depressurization System American Institute of Steel Construction American Iron and Steel Institute As-Low-As-Reasonably Achievable Advanced Light Water Reactor Air Movement and Control Association American Nuclear Society Argonne National Laboratory American National Standards Institute American Petroleum Institute Air Conditioning and Refrigeration Institute American Society of Civil Engineers American Society of Heating, Refrigeration and Air-Conditioning Engineers American Society of Mechanical Engineers American Society for Testing and Materials Anticipated Transient Without Scram American Welding Society Best Estimate Analyzer for Core Operations - Nuclear Beginning of Life Balance of Plant Branch Technical Position Code of Federal Regulations Critical Heat Flux Crane Manufacturers Association of America Core Makeup Tank Combined Operating License/Combined License Control Rod Drive Control Rod Drive Mechanism Control Support Area Chemical and Volume Control System Design Acceptance Criteria Direct Current Design Basis Accident Design Basis Event Design Control Document EPS-GW-GL Revision 1

4 Table (Sheet 2 of 4) D-EHC DEMA DNB DNBR DOE DPU EFPD EIS EMI EOF EPA EPRI ER ERF ESF ESFAS FID FM FMEA FWPCA GDC GRCA GSI HEPA HFE HVAC I&C ICEA IDCOR IEEE IES ILRT INEL I/O IRWST ISA ISI IST ITAAC Digital Electrohydraulic Control Diesel Engine Manufacturers Association Departure from Nucleate Boiling Departure from Nucleate Boiling Ratio Department of Energy Distributed Processing Unit Effective Full Power Days Environmental Impact Statement Electromagnetic Interference Emergency Offsite Facility Environmental Protection Agency Electric Power Research Institute Environmental Report Emergency Response Facility Engineered Safety Features Engineered Safety Features Actuation System Fixed Incore Detector Factory Mutual Engineering and Research Corporation Failure Modes and Effects Analysis Federal Water Pollution Control Act General Design Criteria/Criterion Gray Rod Cluster Assembly Generic Safety Issues High Efficiency Particulate Air Human Factors Engineering Heating, Ventilation and Air Conditioning Instrumentation and Control Insulated Cable Engineers Association Industry Degraded Core Rulemaking Institute of Electrical and Electronics Engineers Illumination Engineering Society Integrated Leak Rate Test Idaho National Engineering Laboratory Input/Output In-containment Refueling Water Storage Tank Instrument Society of America Inservice Inspection Inservice Testing Inspections, Tests, Analyses and Acceptance Criteria EPS-GW-GL Revision 1

5 Table (Sheet 3 of 4) LBB LOCA LOF LOFT LOOP LOSP LPZ LSB LWR MAAP MCC MCR MCRHS MFCV MFIV M-MIS MOV MPC MSIV MSLB MTBE(F) MW MWe MWt NAE NAS NBS NEC NEI NEMA NFPA NPSH NRC NSSS NUMARC NUREG ORE PCS Leak-Before-Break Loss of Coolant Accident Loss-of-Flow with Failure to Scram Loss of Flow Test Loss of Offsite Power Loss of System Pressure with Degraded ECCS Operation Low Population Zone Last Stage Blade Light Water Reactor Modular Accident Analysis Programs Motor Control Center Main Control Room Main Control Room Habitability System Main Feedwater Control Valve Main Feedwater Isolation Valve Man-Machine Interface System Motor-operated Valve Maximum Permissible Concentration Main Steam Isolation Valve Main Steam Line Break Mean Time Between Event (Failure) Megawatt Megawatt, electric Megawatt, thermal National Academy of Engineering National Academy of Sciences National Bureau of Standards National Electrical Code Nuclear Energy Institute National Electrical Manufacturers Association National Fire Protection Association Net Positive Suction Head Nuclear Regulatory Commission Nuclear Steam Supply System Nuclear Management and Resources Council (Superseded by NEI) Report designator for NRC reports Occupation Radiation Exposure Passive Containment Cooling System EPS-GW-GL Revision 1

6 Table (Sheet 4 of 4) P&ID PRA PRHR PRHR HX PWR PXS QA RAM RAP RCS RCDT RFI R.G. RNS RSW RV SECY SER SMACNA SRP SSAR SSD SSI SSE SUFCV SUFIV TID TMI TSC UBC UL UPS URD USI USPHS WCAP Piping and Instrumentation Diagram Probabilistic Risk Assessment Passive Residual Heat Removal Passive Residual Heat Removal Heat Exchanger Pressurized Water Reactor Passive Core Cooling System Quality Assurance Reliability, Availability, Maintainability Reliability Assurance Program Reactor Coolant System Reactor Coolant Drain Tank Radio Frequency Interference Regulatory Guide Normal Residual Heat Removal Remote Shutdown Workstation Reactor Vessel Secretary of the Commission Letter Safety Evaluation Report Sheet Metal and Air Conditioning Contractors National Association Standard Review Plan Standard Safety Analysis Report System Specification Document Soil Structure Interaction Safe Shutdown Earthquake Startup Feedwater Control Valve Startup Feedwater Isolation Valve Total Integrated Dose Three Mile Island Technical Support Center Uniform Building Code Underwriters Laboratories Uninterruptible Power Supply Utility Requirements Document Unresolved Safety Issue United States Public Health Service Westinghouse report designator, originally Westinghouse Commercial Atomic Power EPS-GW-GL Revision 1