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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 />

Level 1 <strong>for</strong> SFP fuel damage frequency that most precisely reflect the actual state <strong>of</strong> the units are<br />

provided in Table 1.7-1 below (events per reactor year).<br />

Table 1.7-1 <strong>Summary</strong> results <strong>of</strong> the fuel damage frequency in SFP<br />

Initiating event category<br />

SFP fuel damage frequency [ per year]<br />

Internal initiating events<br />

2,0E-05<br />

Seismic impact<br />

1,9Е-06<br />

Fire impact<br />

2,3Е-06<br />

Total SFP fuel damage frequency<br />

2,4E-05<br />

The main contributors to the risk <strong>of</strong> damage to the fuel in the SFP, related to the internal<br />

initiating events are the initiators "Leakage from SFP", 48% <strong>of</strong> total risk, and "Loss <strong>of</strong> <strong>of</strong>f-site<br />

power" and "Loss <strong>of</strong> non-service water", with 22%.<br />

On the basis <strong>of</strong> PSA Risk Monitor was developed, which is used in the daily operation <strong>of</strong><br />

units 3 and 4 <strong>of</strong> <strong>Kozloduy</strong> <strong>NPP</strong>. Furthermore, other PSA applications were developed, such as<br />

probabilistic assessment <strong>of</strong> operational events.<br />

It should be noted that the above estimates <strong>of</strong> the current state <strong>of</strong> the units are too<br />

conservative, given the constantly decreasing heat in the assemblies and additional technical and<br />

organizational measures <strong>for</strong> the prevention and mitigation <strong>of</strong> potential emergency situations. These<br />

measures were developed after bringing the unit in state "SNF storage in SFP" and are not reported<br />

in PSA [34], [35].<br />

1.7.2 Scope and main results <strong>of</strong> Units 5 and 6 PSA<br />

The first probabilistic safety assessment <strong>for</strong> VVER-1000 reactors ever was per<strong>for</strong>med <strong>for</strong><br />

units 5 and 6 <strong>of</strong> <strong>Kozloduy</strong> <strong>NPP</strong>. Since multiple tests have been extended in the scope, methodology<br />

and structure. The aim was to reflect both the current state <strong>of</strong> the plant, after numerous upgrades,<br />

and the development <strong>of</strong> analyses methods. The results <strong>of</strong> PSA Level 1 in the table below represent<br />

the state at the time:<br />

60/202

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