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Summary Report for Conduct of Kozloduy NPP Stress Tests

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“<strong>Kozloduy</strong> <strong>NPP</strong>” PLC<br />

SUMMARY REPORT<br />

<strong>for</strong> <strong>Conduct</strong> <strong>of</strong> <strong>Kozloduy</strong> <strong>NPP</strong><br />

<strong>Stress</strong> <strong>Tests</strong><br />

2.10.5 Evaluation <strong>of</strong> safety margins against earthquake <strong>for</strong> DSFS<br />

According to analysis per<strong>for</strong>med [44], it follows that the relative units <strong>of</strong> DSFS margin are<br />

0,11g or 55% <strong>of</strong> the design DBE that <strong>for</strong> the nuclear installation is 0,2g, i.e. DSFS can withstand<br />

without damage to the fuel an earthquake 1,55 greater than the design DBE.<br />

2.10.5.1 Assessment <strong>of</strong> the seismic impact leading to severe fuel damage<br />

Based on engineering evaluation given in [44] it can be summarized that DSFS can per<strong>for</strong>m<br />

its functions <strong>for</strong> spent fuel safe storage to seismic accelerations <strong>of</strong> about 0,31 g, then collapse <strong>of</strong> the<br />

main support structure can be anticipated. Extension <strong>of</strong> safe storage <strong>of</strong> the fuel in this situation<br />

depends on the possibility <strong>of</strong> cleaning <strong>of</strong> the constriction debris and restoring, if possible, the<br />

natural ventilation.<br />

2.10.5.2 Scenario with beyond design basis earthquake followed by beyond design basis<br />

flooding<br />

According to the results <strong>of</strong> [89], no SSCs will be affected by MWL. There<strong>for</strong>e, <strong>for</strong> this<br />

nuclear installation scenario with combination <strong>of</strong> beyond design basis earthquake with beyond<br />

design basis flooding is not considered as the effect <strong>of</strong> the external events has been defined under<br />

[44].<br />

2.10.5.3 Measures to enhance DSFS robustness<br />

With regard to DSFS measures to increase robustness are not proposed as its margin is fully<br />

dependent on the capacity <strong>of</strong> the civil structure.<br />

2.11 CONCLUSION FOR EVALUATION OF THE INFLUENCE OF SEISMIC IMPACTS<br />

ON THE SITE OF KOZLODUY <strong>NPP</strong><br />

According to the review <strong>of</strong> the seismic characteristics <strong>of</strong> <strong>Kozloduy</strong> <strong>NPP</strong> site reevaluated in<br />

1992 (Project BUL 9/012 "Site and Seismic Safety <strong>of</strong> <strong>Kozloduy</strong> and Belene <strong>NPP</strong>s") and additional<br />

studies <strong>of</strong> 1995 (Studies <strong>for</strong> local earthquakes and probabilistic determination <strong>of</strong> seismic effects <strong>for</strong><br />

seismic PSA) it can be concluded that the re-evaluated seismic bases at the site comply with current<br />

regulations.<br />

The safety related equipment involved in the emergency scenarios <strong>for</strong> seismic resistance,<br />

defined as parameters <strong>of</strong> functions describing its conventional probability <strong>of</strong> failure (fragility<br />

curves) is are analized. Limits <strong>of</strong> seismic accelerations that any nuclear facility can withstand<br />

without severe damage to the fuel and disposal <strong>of</strong> radioactive substances into the environment are<br />

defined.<br />

It follows from the above findings that the analysis <strong>of</strong> beyond design basis seismic impact is<br />

sufficiently conservative and gives confidence that in seismic terms the SSCs <strong>of</strong> <strong>Kozloduy</strong> <strong>NPP</strong> are<br />

able to ensure the safety <strong>of</strong> the plant <strong>for</strong> real maximum seismic impacts probable <strong>for</strong> the site.<br />

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