Published 1995 | Version v1
Report Open

Methodology and results of the seismic probabilistic safety assessment of Krsko nuclear power plant

  • 1. Westinghouse Energy Systems Europe, Brussels (Belgium)
  • 2. EQE International, Irvine, CA (United States)

Description

A seismic IPEEE (Individual Plant Examination for External Events) was performed for the Krsko plant. The methodology adopted is the seismic PSA (Probabilistic Safety Assessment). The Krsko NPP is located on a medium to high seismicity site. The PSA study described here includes all the steps in the PSA sequence, i.e. reassessment of the site hazard, calculation of plant structures response including soil-structure interaction, seismic plant walkdowns, probabilistic seismic fragility analysis of plant structures and components, and quantification of seismic core damage frequency (CDF). Also relay chatter analysis and soil stability studies were performed. The seismic PSA described here is limited to the analysis of CDF (level I PSA). The subsequent determination and quantification of plant damage states, containment behaviour and radioactive releases to the outside (level 2 PSA) have been performed for the Krsko NPP but are not further described in this paper. The results of the seismic PSA study indicate that, with some upgrades suggested by the PSA team, the seismic induced CDF is comparable to that of most US and Western Europe NPPs. (author)

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Part of:
Seismic evaluation of existing nuclear facilities. Proceedings

Additional details

Publishing Information

Imprint Title
Seismic evaluation of existing nuclear facilities. Proceedings
Imprint Pagination
454 p.
Journal Page Range
p. 407-434
Report number
INIS-XA--185

Conference

Title
SMIRT-13 post conference seminar no. 16. Advanced technology seminar on seismic evaluation of existing nuclear facilities
Dates
21-23 Aug 1995
Place
Iguazu (Argentina)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
30053332
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT; KRSKO REACTOR; MECHANICAL STRUCTURES; PROBABILISTIC ESTIMATION; REACTOR COMPONENTS; RISK ASSESSMENT; SAFETY ANALYSIS; SEISMIC SURVEYS; SEISMOLOGY
Descriptors DEC
ENRICHED URANIUM REACTORS; GEOLOGIC SURVEYS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
4 refs, 7 figs