The Failure Mode Studies And Application Of Reactor Coolant Pump In Million Kilowatts Level Of Pressurized Water Reactor Nuclear Power Station

The Reactor Coolant Pump in nuclear power stations is acomponent of the primary loop pressure boundary and the mostcritical rotating equipment in nuclear island, its security,stability, and long-term reliable operation requirements inhigh-temperature, high-pressure and radiation conditions. It’sa high technology system. According to the types and technologydevelop course of Reactor Coolant Pump, specifically for it’sphysical design and operational feature，Studies mainly on failuremode of Reactor Coolant Pump has carried out in thisarticle.According to the Fault Tree Analysis,the Fault Tree ofReactor Coolant Pump was established，And the main failure modehas been distinguished in view of the qualitative analysis andthe quantitative analysis for the Fault Tree.According to the main failure mode of the Reactor CoolantPump in Million Kilowatts Level of Pressurized Water ReactorNuclear Power Station,The article gives the technologicalsolution to handle all these representative malfunctions.Thetechnological solution was applied in Daya Bay nuclear powerstation,and we solves the representative malfunctionssuccessfully,which includes the No.1seal leakage abnormal,oillevel of motor abnormally and high vibration etc.These goodpractice ensures the safety and stabilizes of Reactor Coolant Pumpin operation. Also,the technological measure dealing with the oillevel abnormal belongs to the innovative type,which is in the leadof the maintainence and operation field of Reactor Coolant Pump.The optimization for maintainence tactics was made in thearticle owing to the practice in DAYABAY. According to the Fault Treeand the comparative analysis,The article gives the technological suggestion about maintainence period and critical monitoringstrategy dealing with the shaft crack on type100Reactor CoolantPump. And the technological suggestion will be confirmed in formalprocedure. For the internal change-out of Model100Reactor CoolantPump in Daya Bay,The article dicusses,analyzes the process andtechnical key of internal change-out. according to the analysis andthe practices in Daya Bay,the article introduces the optimizationin performing of the internal change-out which has shortened theprocess and controlled the risk effectively.and the out-tage ofpower station will also benefit from the optimization.Thestandard process and the duration of internal change-out should beat the Level of world in the lead.The studies and it’s application of this task have beencarried out and got effective achievement in Daya Bay nuclear powerstation.