Published December 1994 | Version v1
Report

ENEL position on digital control and protection systems for new generation nuclear power plants and related safety implications

Creators

  • 1. ENEL, Rome (Italy)

Description

The present paper briefly describes the architecture of the C and PS and its safety implications and solutions ENEL intends to adopt in designing the new NPPs. This architecture is based on extended use of Digital Technology and Human Factor techniques, with computerized control rooms provided of software driven work stations, connected to the field through a hierarchical multi-level network system. The same approach is being adopted also for the dual-cycle thermal plants presently under construction and therefore the design of I and C and M-MIS will profit of the experience that will be gained in this field in the coming years. However, despite proper design and operation, software based systems maintain a high vulnerability to latent faults affecting mainly the software. ENEL approach to cope with digital system faults is based on both the principles of high reliability: fault avoidance and fault tolerance. Fault avoidance is pursued mainly by adopting a very systematic and thorough design process, stringent requirements on hardware component reliability and severe and complete software Q and A and V and V. Fault tolerance is pursued by redundancy, segmentation of control and protection functions, physical separation among redundant channels, environmental compatibility. Last but not least, a diverse protection system for the most important prevention and mitigation functions is considered, based on a simple and proven conventional technology. (author). 4 refs, 5 fig, 2 tabs

Part of:
Safety assessment of computerized control and protection systems. Report of a technical committee meeting held in Vienna, 12-16 October 1992

Additional details

Publishing Information

Imprint Title
Safety assessment of computerized control and protection systems. Report of a technical committee meeting held in Vienna, 12-16 October 1992
Imprint Pagination
98 p.
Journal Page Range
p. 69-84.
ISSN
1011-4289
Report number
IAEA-TECDOC--780

Conference

Title
Technical committee meeting on safety assessment of computerized control and protection systems.
Dates
12-16 Oct 1992.
Place
Vienna (Austria).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
26030386
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTER ARCHITECTURE; COMPUTERIZED CONTROL SYSTEMS; CONTROL ROOMS; DESIGN; DIGITAL SYSTEMS; FAILURES; HUMAN FACTORS; MODIFICATIONS; NUCLEAR POWER PLANTS; QUALITY ASSURANCE; REACTOR PROTECTION SYSTEMS; SAFETY ANALYSIS
Descriptors DEC
CONTROL SYSTEMS; ENGINEERED SAFETY SYSTEMS; NUCLEAR FACILITIES; ON-LINE CONTROL SYSTEMS; ON-LINE SYSTEMS; POWER PLANTS; THERMAL POWER PLANTS

Optional Information