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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 />

The power supply <strong>of</strong> the pump and the I&C is from mobile diesel-generator.<br />

The suction pipeline <strong>of</strong> the pump is connected through a T-joint to the suction pipeline <strong>of</strong> the<br />

pump <strong>of</strong> the first channel <strong>of</strong> steam generator emergency makeup water system. The pump<br />

connection is provided through one manual valve. The pressure pipeline is connected to the pressure<br />

header <strong>of</strong> the pump <strong>of</strong> the first channel <strong>of</strong> steam generator emergency makeup water system.<br />

Design solutions <strong>for</strong> systems <strong>for</strong> heat removal to the ultimate heat sink<br />

Essential components service water system.<br />

The system serves <strong>for</strong> water supply to the safety system components. It includes spray ponds<br />

that remove heat to the atmosphere, pumps and pipelines to the heat-exchangers. The system is a<br />

part <strong>of</strong> the safety system.<br />

Low pressure emergency and normal cooldown system.<br />

The low pressure emergency and normal core cooldown system combine the functions <strong>of</strong> a<br />

protective safety system and a normal operation system (section 12 from [7],[8]) . The system is<br />

designed <strong>for</strong>:<br />

· reactor core emergency cooldown and continued core heat removal in accidents<br />

conditions associated with primary circuit leakage, including main circulation line break that<br />

ensures supply to the primary circuit <strong>of</strong> boric acid with concentration over 16 g/kg with flow<br />

rate 250-300 m 3 /h at primary circuit pressure ≤ 2.16 MPa and 700-750 m 3 /h at primary<br />

circuit atmospheric pressure.<br />

· primary circuit normal cooldown during reactor shutdown and core decay heat<br />

removal at maintenance and refuelling.<br />

The system is a part <strong>of</strong> the safety system and consists <strong>of</strong> three independent trains with each<br />

train providing <strong>for</strong> 100% <strong>of</strong> the system functions.<br />

BRU-A system.<br />

The system <strong>of</strong> fast acting device <strong>for</strong> the steam dump to the atmosphere is designed to release<br />

steam from the main steam lines to the atmosphere. The heat is removed from the SGs directly to the<br />

atmosphere at steam cooldown <strong>of</strong> the primary circuit. BRU-A system is an emergency system and is<br />

used when BRU-K system is not operable. The use requires replenishment <strong>of</strong> large amount <strong>of</strong> water<br />

in the SG makeup system. SG makeup at BRU-A operation is through makeup water systems listed<br />

in the preceding paragraph.<br />

Intermediate level emergency boron supply system.<br />

This is a protective system that is a part <strong>of</strong> the safety systems designed <strong>for</strong> emergency<br />

primary circuit supply with boric acid solution with initial concentration <strong>of</strong> 40 g/kg and flow-rate<br />

over 130 m 3 /h, at accident conditions with high pressure (≤ 110 kgf/ m 2 ) maintained in the primary<br />

circuit as well as <strong>for</strong> replenishment <strong>of</strong> leakages in modes with the primary circuit depressurized.<br />

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