17.04.2015 Views

Summary Report for Conduct of Kozloduy NPP Stress Tests

Summary Report for Conduct of Kozloduy NPP Stress Tests

Summary Report for Conduct of Kozloduy NPP Stress Tests

SHOW MORE
SHOW LESS

Create successful ePaper yourself

Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.

“<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 />

Spent Fuel Pools (SFP) are located in the containments and serve to store and maintain the<br />

spent fuel (to reduction <strong>of</strong> decay heat to the permissible level) during not less than three years.<br />

By 30.06.2011 in SFP 5 355 fuel assemblies and in SFP 6 365 fuel assemblies are stored.<br />

SFP cooling systems are the part <strong>of</strong> units 5 and 6 systems. Correspondingly normal and<br />

standby power supply SFP cooldown system <strong>of</strong> units 5 and 6 is similar to normal and standby<br />

power supply to the reactor installations. These systems are classified safety related normal<br />

operation systems. These are three-train systems (redundancy 3 х 100%) and are powered from the<br />

emergency DGs.<br />

5.2.1.1.2 Independence <strong>of</strong> emergency power supply sources and measures to prolong<br />

operational time<br />

With two emergency DGs in operation (one per unit) total reserve <strong>of</strong> fuel and oil <strong>of</strong> the<br />

emergency DGs is sufficient <strong>for</strong> more than 38 days.<br />

5.2.1.2 Loss <strong>of</strong> <strong>of</strong>f-site power supply and loss <strong>of</strong> emergency DG<br />

The following Table provides the times <strong>for</strong> heating and evaporation <strong>of</strong> water to the level <strong>of</strong><br />

the heated part <strong>of</strong> the assemblies in case <strong>of</strong> loss <strong>of</strong> <strong>of</strong>f-site and emergency power. Two options <strong>for</strong><br />

different fuel quantities have been considered. The first one <strong>for</strong> the current amount <strong>of</strong> spent fuel by<br />

30.06.2011 and the second with full fuel removed from the core in the SFP after the reactor is taken<br />

out <strong>for</strong> a refuelling outage. The initial level in the SFP in each case is considered the one adequate<br />

<strong>for</strong> normal operation +28.80 m.<br />

If the additional DG is available, durations specified in the table prolong at least to 19 hours<br />

due to usage <strong>of</strong> water reserves in the boron control system tanks.<br />

Table 5.2-1: Time to occurrence <strong>of</strong> the main events in SFP in case <strong>of</strong> complete loss <strong>of</strong> alternate<br />

current power supply.<br />

Parameter SFP 5 SFP 6<br />

Without unloading <strong>of</strong> the core<br />

Only spent fuel<br />

Time <strong>for</strong> heating to 50ºC to 100ºC [h:min] 22:52 39:53<br />

Time from 50ºC to start <strong>of</strong> uncoverage <strong>of</strong> the fuel<br />

assembly [h:min]<br />

Spent fuel and unoaded core<br />

136:21<br />

(more than 5 days)<br />

237:47<br />

(more than 9 days)<br />

Time <strong>for</strong> heating to 70ºC to 100ºC [h:min] 1:52 1:48<br />

Time from 70ºC to start <strong>of</strong> uncoverage <strong>of</strong> the fuel<br />

assembly [h:min]<br />

17:28 16:51<br />

154/202

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!