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 formFiles
36087593.pdf
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(3.3 MB)
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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