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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 />

These sets have developed instructions <strong>for</strong> actions <strong>for</strong> response to emergency conditions in<br />

SFP in modes “MAINTENANCE OUTAGE” and “REFUELLING” [in. №РБОК-0, „ACTIONS<br />

FOR RESPONSE TO EMERGENCY CONDITIONS IN SFP (TG21B01,02,03) IN MODES<br />

“MAINTENANCE OUTAGE” И “REFUELLING”].<br />

For conducting <strong>of</strong> training full-scale simulator <strong>of</strong> units 5 and 6 (FSS 1000) is used which<br />

maintained in accordance with reference – unit 6, according to requirements <strong>of</strong> the regulatory<br />

authority and standards set in ANSI/ANS-3.5-1998.<br />

Two types <strong>of</strong> training is delivered to the operators <strong>of</strong> the MCR - refreshment and<br />

introductory <strong>for</strong> licensing.<br />

Introductory training <strong>for</strong> licensing <strong>of</strong> SRO, NUDE, CD <strong>NPP</strong> and RPh has various durations<br />

according to: „Regulation on conditions and procedure <strong>for</strong> enhancing <strong>of</strong> pr<strong>of</strong>essional qualification<br />

and procedure on issuing licenses <strong>for</strong> specialized training and certificates <strong>for</strong> authorization <strong>for</strong> use<br />

<strong>of</strong> nuclear energy”.<br />

Refreshment training <strong>of</strong> the operators <strong>of</strong> the MCR is held according to preliminary approved<br />

schedule twice annually with durations <strong>of</strong> 5 training days. Training scenarios are developed on the<br />

basis <strong>of</strong> analysis <strong>of</strong> events which occurred at various <strong>NPP</strong>s, considering probability <strong>of</strong> such failures<br />

at units 5 and 6. Training is held by the licensed instructors. During the training on FSS 1000, the<br />

teams are trained to work on SBEOP to bring the reactor installation into steady-state and safe<br />

condition.<br />

For severe accident management at Units 5 and 6 guidelines were developed <strong>for</strong> severe<br />

accidents (SAMG), which follow the <strong>for</strong>mat <strong>of</strong> SBEOP. Criteria were defined <strong>for</strong> transfer from<br />

SBEOP to SAMG.<br />

SAMGs <strong>for</strong> Units 5 and 6 were developed on the basis <strong>of</strong> system analysis <strong>of</strong> the processes<br />

and phenomena during severe accidents [148]. The purpose <strong>of</strong> system analysis is to define the basis<br />

<strong>for</strong> knowledge <strong>of</strong> processes and phenomena, occurring at progress <strong>of</strong> severe accidents, all the<br />

technical means (equipment and systems), which allow <strong>for</strong> reaching <strong>of</strong> the set purposes in the<br />

course <strong>of</strong> severe accident management (SAM).<br />

Strategies defined <strong>for</strong> severe accident management are the following:<br />

· Pressure reduction in the primary circuit;<br />

· Pressure reduction in the secondary circuit;<br />

· Water injection to the primary circuit;<br />

· Water injection to the secondary circuit;<br />

· Pressure reduction in the containment.<br />

SAMG includes three step-by-step procedures at the MCR:<br />

· SAMG-00 Loss <strong>of</strong> 6 kV sources <strong>of</strong> electric power supply;<br />

· SAMG-01 Initial actions at severe accident;<br />

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