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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 />

supply boric acid solution through the primary circuit makeup and blowdown system and need <strong>for</strong><br />

attenuation <strong>of</strong> reactor at primary circuit high pressure (9-18 MPa).<br />

Intermediate pressure emergency boron injection system.<br />

The system is designed <strong>for</strong> emergency injection <strong>of</strong> emergency boric acid solution to the<br />

primary circuit with concentration <strong>of</strong> 40 g/kg in case <strong>of</strong> loss <strong>of</strong> <strong>of</strong>f-site power or in case <strong>of</strong> failure to<br />

supply boric acid solution through the primary circuit makeup and blowdown system and need <strong>for</strong><br />

attenuation <strong>of</strong> reactor at primary circuit intermediate pressure (below 11 MPa).<br />

1.3.2.1.2 Systems ensuring core criticality with the reactor depressurized<br />

With the reactor depressurized and presence <strong>of</strong> fuel in the core be<strong>for</strong>e and after refuelling<br />

criticality <strong>of</strong> the core is provided the control rods in fuel and the boric acid solution solution with<br />

concentration ≥ 16 g/kg circulating in the primary circuit and emergency and normal cooling<br />

system. Material balance <strong>of</strong> the coolant can be maintained by boron solution from primary circuit<br />

emergency makeup tank (EMT).<br />

During refuelling the material balance <strong>of</strong> the entire system consisting <strong>of</strong> fuel storage pool,<br />

reactor, primary circuit and emergency and normal cooldown system is maintained with boric acid<br />

solution with concentration ≥16 g/kg through SFP water filter purification system or reactor building<br />

boron containing water system.<br />

The fuel sub-criticality during all stages <strong>of</strong> refuelling outage measures is ensured by taking<br />

measures to prevent from penetration <strong>of</strong> clean condensate to the reactor circuit and SFP and to carry<br />

out automatic and manual physical and chemical monitoring <strong>of</strong> the coolant content.<br />

1.3.2.1.3 Systems ensuring fuel storage pool sub-criticality<br />

The spent fuel sub-criticality <strong>for</strong> at least 5% in SFP is ensured through: reliable remoting <strong>of</strong><br />

the cells <strong>for</strong> storage during the entire period <strong>of</strong> operation <strong>of</strong> the SFP; use <strong>of</strong> homogenous absorber on<br />

the water <strong>of</strong> SFP with boric acid solution with concentration 16 g/kg; use <strong>of</strong> effective fixed<br />

heterogenuous absorbers that do not lose their properties in the process <strong>of</strong> operation. The cells <strong>for</strong><br />

assemblies are designed from borated stainless steel. The absorbing capacity (at burnup <strong>of</strong> 10 B and<br />

wall depth reduction due to the corrosion) <strong>of</strong> the racks cells is preserved during the entire service<br />

life.<br />

Maintaining the level and water chemistry <strong>of</strong> the SFP is ensured by SFP water purification<br />

system. At fuel storage the level is maintained at height +28.8 m with total volume <strong>of</strong> 585 m 3 . In<br />

refuelling mode SFP is connected to the refuelling shaft and the water level is maintained at the<br />

height <strong>of</strong> +36.2 m which requires additional water inventory (about 1400 m 3 ) ensured by SFP water<br />

purification system.<br />

1.3.2.2 Reactor Heat Removal to the Ultimate Heat Sink<br />

1.3.2.2.1 Heat removal logics<br />

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