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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 />

5 LOSS OF POWER SUPPLY AND LOSS OF ULTIMATE HEAT SINK<br />

In this section results are summarized <strong>of</strong> the analyses <strong>of</strong> the response and robustness <strong>of</strong> the<br />

nuclear installations at the <strong>Kozloduy</strong> <strong>NPP</strong> in case <strong>of</strong> loss <strong>of</strong> the power supply and loss <strong>of</strong> ultimate<br />

heat sink. Attention is paid to the design solutions applied to prevent occurrence <strong>of</strong> such events, and<br />

to response <strong>of</strong> the facilities at sequential degradation <strong>of</strong> the following safety functions specified in<br />

Art. 33 <strong>of</strong> [43]:<br />

· Removal <strong>of</strong> decay heat from the reactor core at specific operational conditions and<br />

accidents with maintaining reactor coolant circuit boundaries;<br />

· Removal <strong>of</strong> heat from safety systems to ultimate heat sink;<br />

· Provision <strong>of</strong> the required safety systems support functions;<br />

· Removal <strong>of</strong> decay heat from spent fuel, storage outside the reactor core, but within<br />

the boundaries <strong>of</strong> the power unit.<br />

Assessment is provided <strong>for</strong> the time period available to the operator to execute measures to<br />

prevent severe accident at various scenarios.<br />

The following nuclear facilities are subject to the analysis:<br />

· Nuclear reactors <strong>of</strong> units 5 and 6;<br />

· Fuel pool <strong>of</strong> units 5 and 6;<br />

· Fuel pool <strong>of</strong> the shut down units 3 and 4;<br />

· Storage <strong>for</strong> spent nuclear fuel.<br />

The analysis does not cover facility <strong>for</strong> spent fuel dry storage, as heat removal in it is<br />

provided on the passive principle, and as an ultimate heat sink ambient air is used.<br />

5.1 NUCLEAR REACTORS – UNITS 5 AND 6<br />

5.1.1 Loss <strong>of</strong> power supply<br />

5.1.1.1 Loss <strong>of</strong> <strong>of</strong>f-site power supply<br />

Operational power supply to units 5 and 6 is provided through the auxiliaries trans<strong>for</strong>mers,<br />

energized by the generator voltage. Standby power supply is provided from OSY-220 kV. The<br />

second standby power to the units is provided from the standby power supply busbars <strong>of</strong> the other<br />

power unit (unit 5 is powered from unit 6 and vice versa).<br />

Off-site power supply to the bank pumping stations is provided from OSY 220 kV, and the<br />

redundancy is provided from Bukyovtsy substation <strong>of</strong> 110 kV.<br />

5.1.1.1.1 Design schemes at loss <strong>of</strong> <strong>of</strong>f-site power supply, sources, capacity and operability <strong>for</strong><br />

the emergency power supply<br />

EES.<br />

Loss <strong>of</strong> the <strong>of</strong>f-site power is defined as interruption to all the connections with the <strong>NPP</strong> with<br />

139/202

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