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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 />

Analyses <strong>of</strong> the earthquake, flooding, combination <strong>of</strong> beyond design flooding and the<br />

earthquake, loss <strong>of</strong> power supply and loss <strong>of</strong> ultimate heat sink, do not show loss <strong>of</strong> the SSCs,<br />

including ventilation systems.<br />

6.3.2.3 Limitation <strong>of</strong> releases after significant fuel damage in the SFP<br />

Analyses <strong>of</strong> the stress-test on separate positions show that hypothetically only partial,<br />

mechanical failures are possible only not the significant ones <strong>of</strong> fuel in the SFP.<br />

SFP is located in the central hall, outside the SG box compartment and consequently, at<br />

hypothetic fuel damage in the SFP comparatively hostile consequences may be reached in relation<br />

with radioactive releases. Contact <strong>of</strong> the central hall (at destruction) with environment is the cause<br />

<strong>for</strong> the most part <strong>of</strong> releases <strong>of</strong> the radioactive substances during the accident occurring with<br />

containment bypassing. This defeats the purpose <strong>of</strong> strategies <strong>for</strong> maintaining <strong>of</strong> underpressure in<br />

the SGBC.<br />

6.3.2.4 I&C, required <strong>for</strong> monitoring <strong>of</strong> condition <strong>of</strong> fuel in SFP and <strong>for</strong> accident<br />

management<br />

Units 3 and 4 have available the following systems:<br />

· Monitoring system <strong>for</strong> radiation background above SFP.<br />

· Monitoring system <strong>for</strong> temperature and water level in SFP.<br />

· Leakage monitoring system.<br />

Accident does not impact I&C.<br />

6.3.2.5 Accessibility and habitability <strong>of</strong> the MCR<br />

Accessibility and habitability <strong>of</strong> the MCR are not limited at these accidents.<br />

6.3.3 Accident management after uncoverage <strong>of</strong> the upper part <strong>of</strong> fuel in SFP <strong>of</strong> Units 5 and<br />

6<br />

6.3.3.1 Control <strong>of</strong> hydrogen<br />

SFP <strong>of</strong> Units 5 and 6 is located within the containment. Hydrogen which may generate at<br />

possible damage, will spread within the containment and will be recombined by the PAR<br />

6.3.3.2 Ensuring <strong>of</strong> adequate protection against radiation<br />

Radioactive substances which would release at accident in the SFP, will be maintained<br />

within the containment.<br />

6.3.3.3 Limitation <strong>of</strong> releases after significant fuel damage in SFP up to controlled margin<br />

Radioactive substances which would release at accident in SFP will be maintained within<br />

the containment, when the unit is in condition <strong>of</strong> the isolated containment.<br />

In the emergency instruction treating the IEs (initiating events) in the SFP actions are<br />

envisioned <strong>for</strong> evacuation <strong>of</strong> the personnel in the containment and isolation <strong>of</strong> the containment, if<br />

accident occurs in condition <strong>of</strong> the unit with not isolated containment.<br />

193/202

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