Published 1988 | Version v1
Book

Accidents with multiple failures application of physical state approach

  • 1. Electricite de France, 75 - Paris

Description

It is well-known that the event-oriented procedures do not cover every possible accident with any number of instrument or system failures or operator errors. A new approach, based on the relation between the physical state of the reactor and the operator action, has been developed to take into account multiple human and/or system failures, without postulating a time-history transient (1). EDF has applied this new philosophy in two steps. First, the existing event-oriented procedures have been improved and a set of two state-oriented procedures has been introduced, which only interferes in case of failure of the event-oriented procedures. Figure 1 shows, in a severity versus complexity diagramm, how accidental situations are covered by the help of the first generation of state-oriented procedures: a permanent monitoring post-incident procedure (SPI) and an ultimate one (U1). Then, EDF and FRAMATOME (the french manufacturer of the nuclear steam supply system) have verified that it was possible to completely replace event-oriented procedures by a set of state-oriented procedures (figure 1). This second generation of state-oriented procedures, which uses reactor vessel water level instrumentation, is now written and will be implemented at PENLY power station, which will start up in 1989. This paper presents how second generation state-oriented procedures can help the operators to deal with multiple system and/or human failures accidents

Part of:
Proceedings of the international ENS/ANS conference on thermal reactor safety. Volume 2

Additional details

Publishing Information

Publisher
Societe Francaise d'Energie Nucleaire.
Imprint Place
Paris (France)
Imprint Title
Proceedings of the International ENS/ANS Conference on thermal reactor safety. Volume 2
Imprint Pagination
460 p.
Journal Page Range
p. 473-482.

Conference

Title
International ENS/ANS Conference on thermal reactor safety.
Dates
2-7 Oct 1988.
Place
Avignon (France).

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
21020324
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
EMERGENCY PLANS; FAILURES; PHASE DIAGRAMS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; DIAGRAMS; ENRICHED URANIUM REACTORS; INFORMATION; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information