Published March 1994 | Version v1
Report

Influence of PSA methodology on NPP data collection

  • 1. Nuclear Power Plant Research Inst., Trnava (Czech Republic)

Description

Present activities in the field of PSA in the CSFR lead to improvement of the reliability information system (RIS) of all NPP equipment. The creation of a suitable specific reliability database for each NPP with WWER on the basis of existing databases focussing on specific topics is one of the main tasks on NPPs to solve the basis problems of safety improvements. The first part of the article describes the basis aspects and description of the RIS in the innovated version which involved following collection of primary data from NPP: record about the equipment failure; record about the equipment defect; record about the equipment maintenance; record about the safety system tests; record about the operation and outages of the unit and turbo generators; record about the operation and outages of the systems. This data are filled on the NPP by its staff and are elaborated by software ''Complex programme of the following and evaluation of the operational reliability and lifetime of the NPP with WWER selected systems and components''. In the second part of the presented article is showed the preparation and the way of elaborating the Data Base of the Reliability Characteristics for the specific NPP during the PSA project for NPP Dukovany. It is the presentation of the interesting progressive steps of the creation of a Data Base for the PSA project according to the requirements of the safety analytic staff on the basis of present situation in the data collection by the operational staff on an NPP. In the end there is the positive backward influence of PSA project upon practical approach of the operational staff to the operational and maintenance data collection on NPP. (author)

Part of:
Advances in reliability analysis and probabilistic safety assessment for nuclear power reactors

Additional details

Publishing Information

Imprint Title
Advances in reliability analysis and probabilistic safety assessment for nuclear power reactors
Imprint Pagination
264 p.
Journal Page Range
p. 166-172.
ISSN
1011-4289
Report number
IAEA-TECDOC--737

Conference

Title
Technical committee meeting on advances in reliability analysis and probabilistic safety assessment for nuclear power reactors.
Dates
7-11 Sep 1992.
Place
Budapest (Hungary).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
25037050
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DATA ACQUISITION; FAILURES; NUCLEAR DATA COLLECTIONS; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT; SAFETY ANALYSIS
Descriptors DEC
ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information