Published December 1990 | Version v1
Report Open

Detection of incidents and follow-up by the regulatory bodies

Description

Although France has established a large nuclear program based on PWR type reactors, experience gained up to this are are quite modest. Concept of PWR-900 reactors is based mostly on safety analyses and evaluations done a priori. At the time of their construction and start-up they have been considered as advanced safe systems. No data were available concerning any incidents during operation. The Three Mile Island accident in 1979 has changed the attitude concerning reactor safety. The result is the procedure adopted by Electricite de France for follow-up of incident situations during operation of a number of PWR-900 plants. Standardization of this type of NPPs demands extremely strict standards and control of safety systems. This safety analysis procedure consists of the following: analysis of incidents based on data collected by EDF during operation; every regular annual shutdown of a unit is the subject of detailed analysis; together with the detailed analysis, principal elements of operating experience for the series of PWR units are submitted for analysis to a permanent regulatory body

Availability note (English)

Available from INIS in electronic form

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Additional details

Additional titles

Original title (French)
La detection des incidents et le suivi des enseignements par les autorites de surete

Publishing Information

Imprint Pagination
67 p.
Report number
CEA-DAS--767

Conference

Title
INSTN international course on evaluation of operational safety for PWRs
Dates
26 Nov - 14 Dec 1990
Place
Saclay (France)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
36087593
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DATA ANALYSIS; DATA COMPILATION; EXCURSIONS; PWR TYPE REACTORS; REACTOR OPERATION; REACTOR SAFETY; REACTOR SHUTDOWN; SAFETY ANALYSIS
Descriptors DEC
ACCIDENTS; DATA; ENRICHED URANIUM REACTORS; INFORMATION; OPERATION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
11 figs, tabs
Secondary number(s)
INIS-XA-N--094