Nuclear power plants - Instrumentation and control systems important to safety - Criteria for seismic trip system (IEC 63186:2021)

Standard [CURRENT]

DIN IEC 63186:2026-02

VDE 0491-12:2026-02

Nuclear power plants - Instrumentation and control systems important to safety - Criteria for seismic trip system (IEC 63186:2021)

German title
Kernkraftwerke - Leittechnische Systeme mit sicherheitstechnischer Bedeutung - Kriterien für seismische Abschaltsysteme (IEC 63186:2021)
Publication date
2026-02
Accessibility
Original language
German
Pages
20

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Publication date
2026-02
Original language
German
Pages
20
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Overview

Earthquakes represent one of the major external hazards to the safe operation of nuclear power plants. Thus buildings, systems, and components critical to the safety of a nuclear power plant are generally designed to withstand assumed earthquake based on the relevant design criteria. A seismic trip system has been integrated into numerous reactor designs in order to mitigate the adverse effects of a strong earthquake and further enhance reactor safety. This system is intended to shut down the reactor in operation automatically before it is significantly impacted by the vibratory ground motion incurred by strong earthquakes. The standard specifies the minimum requirements for the design of the seismic trip system, and the components thereof, used in a nuclear power plant to mitigate seismic effects. This document is applicable to both the design of new built plants and the upgrading of plants in operation. It may be used for the design of other types of nuclear facilities where normal operation shall be stopped in case of strong seismic motions. The Annex to the standard provides several examples for practical implementation of a seismic trip system.