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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 />

· System <strong>for</strong> service water supply, intended <strong>for</strong> cooling <strong>of</strong> consumers <strong>of</strong> normal<br />

operation systems – ultimate heat sink is Danube river.<br />

· System <strong>for</strong> service water supply, intended to remove heat from equipment <strong>of</strong> the<br />

safety systems during all operational modes and emergency conditions. Each <strong>of</strong> the three<br />

trains <strong>of</strong> the system operate via the self-contained circuit, at this water cooling is provided in<br />

the spray pools. Ultimate heat sink is ambient air.<br />

During power operations <strong>of</strong> the nuclear power units the main ways to remove heat to the<br />

ultimate sink are as follows:<br />

· Through circulation water system – from the turbine condensers to the warm channel<br />

and via it – to the Danube river;<br />

· Through system <strong>for</strong> service water supply to consumers <strong>of</strong> normal operation systems<br />

– to the warm channel and via it – to the Danube river;<br />

· Through system <strong>for</strong> service water supply to consumers <strong>of</strong> the safety systems – to the<br />

spray pools and then – to ambient air.<br />

After the reactor is shut down, fuel decay heat in the core is removed in two stages:<br />

(1) through the secondary circuit, in steam water mode from the hot state to state at which it<br />

is possible to transfer to cooldown via emergency and planned cooldown system.<br />

circuit.<br />

(2) through the primary circuit via emergency and planned cooldown system on cooling<br />

Cooling <strong>of</strong> the safety system consumers is provided through the system <strong>for</strong> service water<br />

supply to safety system consumers to the atmosphere. Subcriticality is maintained by insertion <strong>of</strong><br />

the control rods and by primary boric solution injection systems.<br />

At complete unavailability <strong>of</strong> the secondary circuit systems, reaching <strong>of</strong> the primary circuit<br />

parameters at which it is possible to transfer to operation <strong>of</strong> the cooling circuit, „feed-and-bleed”<br />

procedure may be applied.<br />

During cold condition, the main way to remove heat to the ultimate heat sink is through<br />

service water supply system <strong>of</strong> safety system consumers via the spray pools to the atmosphere.<br />

5.1.3.2 Loss <strong>of</strong> main ultimate heat sink<br />

5.1.3.2.1 Schemes and procedures on heat removal to alternative heat sinks<br />

At loss <strong>of</strong> access to the Danube river due to simultaneous loss <strong>of</strong> BPS and/or low-pressure<br />

channels and emergency pump station and its pipelines to the emergency volume, in these cases<br />

heat release from the core <strong>of</strong> each <strong>of</strong> the nuclear reactors 5 and 6 is provided via self-contained<br />

circuit through the service water supply system to the safety systems consumers through the spray<br />

pools to the atmosphere.<br />

148/202

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