BS 4877:2016

Foreword
1 Scope
2 Normative references
3 Terms, definitions and abbreviations
4 General I&C design principles
5 I&C systems
6 Reactor and plant instrumentation
7 Secondary circuit, turbine and electrical systems
8 Design recommendations
Annexes
Annex A (informative) - Nuclear power plants - I&C
        systems - A guide to applicable standards
Bibliography

Gives recommendations for determining the I&C design and identifying the I&C systems and measurements required on a nuclear reactor plant, including the equipment required for reactor safety and protection, automatic control, and for the information and control in the main and supplementary control rooms of the nuclear reactor plant.

This British Standard provides recommendations for determining the I&C design and identifying the I&C systems and measurements required on a nuclear reactor plant, including the equipment required for reactor safety and protection, automatic control, and for the information and control in the main and supplementary control rooms of the nuclear reactor plant. This British Standard provides recommendations for a clear life cycle for the design and implementation of control and instrumentation systems. This includes the documentation of the I&C design basis, classification of functions according to their safety importance, identification of a fault schedule and of internal and external hazards such as fire, environmental and seismic events or flood. This British Standard also provides recommendations for the main I&C systems on the plant and control rooms including: sensors; actuator interface operation; measurements; measurement methods; the reactor protection system; control and display facilities for reactor control and instrumentation; and power supplies and communication systems. This British Standard does not cover commercial or managerial matters, the measurement and control of radioactivity releases, or the specific faults that require protection. It does not cover refuelling systems, the emergency control centre or technical support centre, off-site support for emergencies, or what constitutes an acceptable radiological risk.