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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 />

pumps are located in CPS 3 and 4. The emergency makeup <strong>of</strong> the spray pools is provided from 6<br />

shaft pump station (ShPS) in the valley <strong>of</strong> Danube River.<br />

On the other hand, at loss <strong>of</strong> group A service water supply system reactor fuel cooling can<br />

be ensured by use <strong>of</strong> alternative system <strong>for</strong> SG makeup, and SFP fuel cooling can be ensured by<br />

SFP flooding system.<br />

The Shaft Pump Stations 1¸6 are powered from BPS by cable-overhead lines 6kV with<br />

process name ShPS-A and ShPS-B. ShPS-A is powered from the V 6kV section <strong>of</strong> BPS. ShPS-B is<br />

powered from the IX 6kV section “Uninterruptible power supply”. Procedure <strong>for</strong> temporary power<br />

supply <strong>of</strong> ShPS-А outlet to ShPS <strong>of</strong> diesel-generator <strong>of</strong> BPS.<br />

2.5.3.4 Other indirect impacts caused by fires or explosions<br />

2.5.3.4.1 Internal floodings due to seismic causes – at the site or in the buildings<br />

In this review existing analyses <strong>of</strong> hazards from internal floodings as well as seismic<br />

qualification status <strong>of</strong> the site and buildings pipelines has been assessed.<br />

Measures are provided to prevent from adverse effects on the plant safety from internal<br />

flooding resulting from rupture <strong>of</strong> non-seismically qualified pipelines in the site <strong>of</strong> the buildings.<br />

2.5.3.4.1.1 Analyses <strong>of</strong> consequences <strong>of</strong> internal floodings in reactor building outside the<br />

containment turbine hall<br />

Under the modernization programme analyses <strong>of</strong> consequences <strong>of</strong> internal flooding were<br />

per<strong>for</strong>med, [86]. Individual analyses <strong>of</strong> flooding <strong>of</strong> rooms <strong>for</strong> all respective fluid systems located in<br />

the reactor building outside the containment, Appendices 5 to 24 [86], <strong>for</strong> turbine hall, Appendices<br />

25 [86] were developed. Appendix 26 [86] specified the differences <strong>for</strong> unit 5 as the study is<br />

per<strong>for</strong>med based on unit 6. For each room conclusions are provided depending on the influence <strong>of</strong><br />

the flooding on the safety system equipment and on the civil structures.<br />

2.5.3.4.2 Measures to cope with fires<br />

According to item 3.3.14 <strong>of</strong> [7],[8] the fire extinguishing system is built in accordance with<br />

the following requirements:<br />

[7],[8]:<br />

· To reduce fire risk;<br />

· To ensure physical separation <strong>of</strong> the systems required <strong>for</strong> the plant safety.<br />

The fire safety system <strong>of</strong> units 5 and 6 consists <strong>of</strong> the following subsystems, item 7.6.1<br />

· External fire ring - Units 5, 6;<br />

· Reactor building and DGS fire alarm and fire extinguishing systems;<br />

· Containment fire alarm and automatic fire extinguishing system;<br />

· Gas fire fighting system in the electric equipment rooms;<br />

78/202

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