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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 />

· Refuelling handling equipment – refuelling machine and 250 t crane in the<br />

containment central hall.<br />

Seismic category 2:<br />

· Spent nuclear fuel storage system water purification system;<br />

· Fresh fuel compartment.<br />

2.4.2 Key operational measures to maintain SFP 3 and 4 in safe state after the earthquake<br />

According to the updated version <strong>of</strong> SAR, [16], [17] measures <strong>for</strong> Units 3 and 4 are<br />

provided and implemented to ensure the required protection against seismic and fire impacts.<br />

Additionally to ensure the safe and secure storage <strong>of</strong> fuel in SFP seismic qualification <strong>of</strong> the<br />

systems ensuring its functioning (SFP civil structure; SFP racks [53]; SFP flooding system; SFP<br />

cooldown system; SFP overflow line to emergency makeup tank (EMT); universal slot line the<br />

EMT; universal slot drain line to EMT (AB); SFP emergency flooding system) [54], [55] was<br />

per<strong>for</strong>med. The updated analysis <strong>of</strong> postulated initiating events <strong>for</strong> the units in state “E” according<br />

to the regulation <strong>for</strong> spent fuel control [56] shows adherence to the criteria at different water<br />

density, as well as SFP cooldown and flooding system redundancy [54].<br />

The SFP civil structure per<strong>for</strong>ms the design functions, having the required robustness and<br />

carrying capacity at different combinations <strong>of</strong> load, including emergency temperature and seismic<br />

impacts <strong>for</strong> DBE. Also, SFP rack robustness at different modes has been proved [57].<br />

Instructions have been developed, as appendices to [58], [59], specifying personnel actions<br />

and per<strong>for</strong>mance <strong>of</strong> improvement measures only by specific programmes (agreed with the NRA) at<br />

achieving safety limits <strong>for</strong> SFP fuel storage in state Е.<br />

Following the events in Fukushima, according to [60] in the Power Generation 1 a group <strong>of</strong><br />

technical and organizational measures was developed aimed at a comprehensive review and<br />

assessment <strong>of</strong> the current status <strong>of</strong> the safety related equipment [46]. Special emphasis is focused on<br />

the cases with beyond design basis accidents and adverse external and internal impacts at spent<br />

nuclear fuel storage in the SFP in state “E”.<br />

The following measures have been developed and implemented:<br />

· producing list <strong>of</strong> beyond design basis accidents scenarios <strong>for</strong> Units 3 and 4;<br />

· programme <strong>for</strong> Units 3 and 4 operating personnel training in the beyond design basis<br />

accidents scenarios.<br />

68/202

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