Seismic Design and Qualification for Nuclear Power Plants: A Safety GuideThis guide was originally issued as Safety Guide No. 50-SG-S2. It provides details on the design of a nuclear power plant such that earthquakes at the site determined according to Safety Guide No. 50-SG-S1 will not jeopardize its safety. |
Contents
DEFINITIONS | 1 |
GENERAL CONCEPT | 8 |
Mechanical and electrical components 424439 | 22 |
1 other sections not shown
Common terms and phrases
Accident Conditions analytical applicable Atomic Energy Agency Auxiliary feedwater behaviour cable trays CANDU characteristics components containment Control rod core design basis design of nuclear dimensional finite element distribution systems earthquake experience effects ensure equipment evaluation floor response spectrum foundation frequency fundamental frequency ground motion IAEA IAEA PUBLICATIONS important to safety input motion International Atomic Energy Japan liquid Lumped mass main system method modal nuclear facilities nuclear power plants NUCLEAR REGULATORY COMMISSION Nuclear Safety NUSS programme Operational P.O. Box power plant siting power plants 1980 probabilistic safety assessment procedures Protection System Quality assurance radioactive material radioactive waste reactor building reactor coolant Residual heat removal response spectrum safety of nuclear SAFETY SERIES seismic analysis seismic category seismic design seismic input seismic instrumentation seismic qualification shutdown sloshing soil spectra stiffness structures subsystem taken into account tanks typically United Kingdom USNRC ventilation system vibration