ALARA (principle)
Transcription
ALARA (principle)
Appendix-1 Abbreviations and Acronyms ALARA (principle) ASCOT ASME ATHLET (code) ATWS BDBA BRU-A CDF CFR CSNI DAC DB DBA DCH DID DBE DG DGS (diagrams) EBP EC ECCS EdF-CUMULUS EGP EIA EMC EOL EOP EP EPR EPRI EPZ EQ EURATOM EZ FEM (calculations) GILs GSHAP GRS HDR HELB HPME I I0 I0max Imax I&C As Low As Reasonably Achievable (Principle) Assessment of Safety Culture in Organisations Team American Society of Mechanical Engineers Analysis of THermal-hydraulics of LEaks and Transients Anticipated Transients without Scram Beyond Design Basis Accident Main Steam Relief Valve Core Damage Frequency Code of Federal Regulations (US) Committee on the Safety of Nuclear Installations (OECD) Distance Amplitude Correction (curve) Double Ended Break Design Basis Accident Direct Containment Heating Defence in Depth Design Basis Earthquake Diesel Generator Distance Gain Size (diagrams) Extrabudgetary Programme (IAEA) European Commission Emergency Core Cooling System Test facility of Elictricité de France (EdF) Energoprojekt Prague Environmental Impact Assessment Electromagnetic Compatibility, Emergency Management Center End-of-Life Emergency Operating Procedure Emergency Planning European Pressurized Water Reactor Electric Power Research Institute Emergency Planning Zone Equipment Qualification European Atomic Energy Community Earthquake Load/Czech version Finite Element calculations Generic Intervention Levels Global Seismic Hazard Assessment Program Gesellschaft für Reaktorsicherheit und Anlagen Heissdampfreaktor High Energy Line Break High Pressure Melt Ejection local (earthquake) intensity at a given distance from the epicenter epicentral (earthquake) intensity maximum credible epicentral intensity maximium credible local intensity Instrumentation and Control NPP Temelín, Austrian Technical Position Paper, Vienna, July 2001 Appendix-2 Abbreviations and Acronyms IAEA ICISA INSAG IPERS IRR ISI ISP KTA LBB LERF LOCA LPZ LWR MCE Mmax MP MPa MSK MSSV MSIV ND* NDT NEA NEI NPI NPP NRC NRI NSC NUPEC OECD OSART PAR PAZ PGA PHARE PISC PORV POSAR PRISE PSA PSR PSHA PTS PWR PWSCC International Atomic Energy Agency International Commission for Independent Safety Analysis International Nuclear Safety Advisory Group International Peer Review Service (IAEA) Institute of Risk Research In-Service Inspection International Standard Problem Kerntechnischer Ausschuß Leak Before Break Large Early Release Frequency Loss of Coolant Accident Long Term Emergency Planning Zone Light Water Reactor maximum credible earthquake maximum earthquake magnitude Melk Protocol Megapascals Medvedev-Sponheurer-Karnik (seismic intensity scale) Main Steam Line Safety Valves Main Steam Isolation Valve low pressure sequence (late depressurization of primary loop by accident management) Non-Destructive Testing Nuclear Energy Agency Nuclear Energy Institute (US) Nuclear Power International Nuclear Power Plant Nuclear Regulatory Commission Nuclear Research Institute Convention of Nuclear Safety Nuclear Power Engineering Corporation Organisation for Economic Co-operation and Development Operational Safety Review Teams Passive Autocatalytic Recombiners Precautionary Action Zone Peak Ground Acceleration Poland-Hungary Aid for Reconstruction of Economies Programme for the Inspection of Steel Components Power-Operated Relief Valve Pre-Operational Safety Analysis Report Primary to Secondary Leak Probabilistic Safety Assessment Periodic Safety Review Probabilistic Seismic Hazard Assessment Pressurised Thermal Shock Pressurised Water Reactor Primary Water Stress Corrosion Cracking NPP Temelín, Austrian Technical Position Paper, Vienna, July 2001 Appendix-3 Abbreviations and Acronyms QME QV RCC-M RDB RELAP RBMK RSK RPV SA SAM SAMGs SC SCSIN SEOP SG SGCL SGTR Siemens KWU SKI SOAR SONS SORVs SSE STCP STUK SUJB TACIS TNPP TOFD TRL Probe TSC TÜV UBA UPZ USAEC UVE VUJE WENRA WOG WWER (VVER) Qualification of Mechanical Equipment Qualification of Valves French regulations Reaktordruckbehälter Thermohydraulic code used for simulation of transient conditions in PWRs Reaktor Bolshoi Moshchhnoski Kanalkni (High-Power Channel Type Reactor) Reaktor Sicherheits Kommission Reactor Pressure Vessel Severe Accident Severe Accident Management Severe Accident Management Guidelines Richtlinien zum Management schwerer Unfälle Safety Culture Service Central de Sûreté des Installations Nucléaires (Central Department for the Safety of Nuclear Installations) Symptom-oriented Emergency Operating Procedures Steam Generator Steam Generator Collector Leakage Steam Generator Tube Rupture Siemens Kraftwerk Union AG Statens Kårnkraftinspektion Swedish Nuclear Power Inspectorate State of the Art Report State Office for Nuclear Safety Stuck Open Relief Valves Safe Shut Down Earthquake Source Term Code Package Säteilyturvakeskus Státní úřad pro jadernou bezpečnost (State Office for Nuclear Safety) Technical Assistance to the Commonwealth of Independent States Temelín NPP Time Of Flight Diffraction Transmitter-Receiver Longitudinal Probe Technical Support Centre Technischer Überwachungsverein Umweltbundesamt Urgent Protective Action Zone U.S. Army Environmental Center Umweltverträglichkeitserklärung Vyskumny ústav jadrovych elektrarni (Trnava, Czech Republic) Western European Nuclear Regulators' Association Westinghouse Owners Group Water Water Energetic Reactors NPP Temelín, Austrian Technical Position Paper, Vienna, July 2001 Appendix-4 Abbreviations and Acronyms ZAMG ZfP Zentralanstalt für Meteorologie und Geodynamik zerstörungsfreie Werkstoffprüfung NPP Temelín, Austrian Technical Position Paper, Vienna, July 2001