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Summary Report for Conduct of Kozloduy NPP Stress Tests

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 />

SCR (Standby control room) is intended, in case <strong>of</strong> failure to the MCR, <strong>for</strong> reliable transfer<br />

<strong>of</strong> the unit in undercritical cold condition and <strong>for</strong> maintaining the unit in that condition <strong>for</strong> unlimited<br />

time, <strong>for</strong> actuation <strong>of</strong> the safety systems and <strong>for</strong> receiving in<strong>for</strong>mation on condition <strong>of</strong> the reactor.<br />

SCR is located at elevation <strong>of</strong> -4.20 in reactor compartment. The premise <strong>of</strong> the standby<br />

control room is assigned category I <strong>of</strong> the seismic stability. Design accidents related to loss <strong>of</strong><br />

coolant do not affect the MCR. As a result <strong>of</strong> analyses <strong>of</strong> the beyond design seismic impacts the<br />

civil structure <strong>of</strong> the SCR and adjacent premises maintains its integrity. At analyses <strong>of</strong> beyond<br />

design combined impacts <strong>of</strong> the earthquake and <strong>of</strong>f-site flooding is possible - the SCR will be<br />

flooded. At analyses <strong>of</strong> the beyond design impacts <strong>of</strong> <strong>of</strong>f-site flooding it is possible that the adjacent<br />

premises <strong>of</strong> the SCR are flooded what will hinder access to the premise.<br />

6.1.3.3.2 Feasibility and efficiency <strong>of</strong> measures <strong>for</strong> accident management in conditions <strong>of</strong> <strong>of</strong>fsite<br />

hazards (earthquake, flooding)<br />

The design <strong>of</strong> Units 5 and 6 <strong>of</strong> <strong>Kozloduy</strong> <strong>NPP</strong> is robust to impacts <strong>of</strong> the <strong>of</strong>f-site hazards.<br />

The reactor and the main structures <strong>of</strong> the primary circuit are located in the rein<strong>for</strong>ced concrete<br />

containment, intended to localize radioactive products after accident in its own space which is<br />

qualified <strong>for</strong> seismic impacts <strong>of</strong> 0,2 g [7], [8].The main systems and components <strong>of</strong> the safety<br />

systems and these safety-related systems also are located in buildings qualified <strong>for</strong> seismic impacts<br />

0,2g [7], [8]. Analyses <strong>of</strong> beyond design seismic impacts show that to seismic impacts 0.36 g<br />

structures with which accident management are provided, are available. At analyses <strong>of</strong> beyond<br />

design combined impacts <strong>of</strong> the earthquake and <strong>of</strong>f-site flooding it is shown that safety functions<br />

are per<strong>for</strong>med <strong>of</strong> units 5 and 6 with survived equipment. At analyses <strong>of</strong> beyond design impacts <strong>of</strong><br />

the <strong>of</strong>f-site flooding it is shown that systems and equipment required <strong>for</strong> per<strong>for</strong>ming safety<br />

functions, are not affected.<br />

Personnel <strong>of</strong> Units 5 and 6 takes measures in accordance with Emergency procedures <strong>of</strong> the<br />

units to shut down the reactor and maintain it in safe condition. In parallel with the emergency<br />

procedures <strong>of</strong> Units 5 and 6, on-site and <strong>of</strong>f-site emergency response plan will be initiated<br />

according to Appendix 3.2 <strong>of</strong> [28].<br />

6.1.3.3.3 Unavailability <strong>of</strong> the power supply<br />

Impacts <strong>of</strong> unavailability <strong>of</strong> the power supply to Units 5 and 6 <strong>of</strong> the <strong>Kozloduy</strong> <strong>NPP</strong> were<br />

analyzed within assessment <strong>of</strong> loss <strong>of</strong> power supply and loss <strong>of</strong> ultimate heat sink. All the options<br />

were assessed <strong>of</strong> sequential loss <strong>of</strong> sources <strong>of</strong> electric power supply. Virtually availability <strong>of</strong><br />

equipment is reduced <strong>for</strong> accident management, but the design has available sufficient standby<br />

power supply sources, actuation <strong>of</strong> which leads to restoration <strong>of</strong> the equipment required <strong>for</strong> accident<br />

management. Recovery operator actions are described in the Emergency procedures.<br />

6.1.3.3.4 Potential failure <strong>of</strong> measurement instrumentation<br />

183/202

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