Patent Number: 052689395
Section: claims

1. A control system comprising: a nuclear reactor operable for heating water to generate main steam under pressure, and disposed in flow communication with a steam turbine by a main steamline for discharging thereto said main steam;  a plurality of flow control valves disposed in parallel flow communication in said steamline for controlling flow of said main steam from said reactor to said turbine;  a bypass valve disposed in flow communication with said steamline upstream of said control valves and with a condenser of said turbine for selectively bypassing a portion of said main steam as bypass steam around said control valves and turbine to said condenser;  a pressure regulator operatively joined to said control valves and said bypass valve for controlling flow of said main steam to said turbine;  a turbine controller operatively joined to said control valves and said bypass valve for controlling flow of said main steam to said turbine in conjunction with said pressure regulator; and  means for automatically detecting failure of one of said control valves which passes steamflow therethrough at a flowrate below a control valve (CV) flow demand therefor, said failure detecting means being operatively joined to said bypass valve and being effective for opening said bypass valve upon detecting said control valve failure.  a first low value selector operatively joined between said pressure regulator and said turbine controller for receiving a total flow (TF) demand from said pressure regulator and a load demand from said turbine controller, and for selecting the lesser thereof as said CV flow demand for controlling flowrate of said control valves;  a first limiter operatively joined between said pressure regulator and said first selector for providing a predetermined limit to said TF demand;  a second low value selector operatively joined between said first selector and said failure detecting means for receiving said CV flow demand from said first selector and an actual turbine flow signal from sid failure detecting means, and for selecting the lesser thereof as a bypass reference; and  a bypass comparator operatively joined to said first limiter, said second selector, and said bypass valve for obtaining a difference between said TF demand and said bypass reference as a bypass demand, said bypass demand being provided to said bypass valve for controlling operation thereof.  a CV controller operatively joined to said first limiter for receiving therefrom said CV demand, and operatively joined to said control valve for controlling opening thereof;  a position sensor for providing a CV actual position signal of said control valve; and  wherein said failure detection means are operatively joined to said first selector for receiving therefrom said CV demand, and operatively joined to said position sensor for receiving therefrom said CV actual position signal, and effective for comparing said CV demand and said CV actual position signal to detect said CV failure based on a predetermined difference therebetween, and, upon detecting said control valve failure, are effective for generating said actual turbine flow signal based upon said CV actual position signals for said plurality of control valves.  wherein said failure detecting means are operatively joined to said pressure sensor for receiving therefrom said pressure signal, and are effective for comparing said pressure signal with a predetermined reference value thereof to detect said control valve failure based on a predetermined difference therebetween, and, upon detecting said control valve failure, are effective for generating said actual turbine flow signal based upon said pressure signal.  wherein said failure detecting means are operatively joined to said power sensor for receiving therefrom said electrical power signal, and are effective for comparing said power signal with a predetermined reference value thereof to detect said control valve failure based on a predetermined difference therebetween, and, upon detecting said control valve failure, are effective for generating said actual turbine flow signal based upon said electrical power signal.  wherein said failure detecting means are operatively joined to said flow sensors for receiving therefrom said flow signals, and are effective for comparing said flow signals with predetermined reference values thereof to detect said control valve failure based on a predetermined difference therebetween, respectively, and, upon detecting said control valve failure, are effective for generating said actual turbine flow signal based upon said flow signals.  wherein said failure detecting means are operatively joined to said RFCS, and are effective for reducing said reactor recirculation flow for reducing said main steamflow through said steamline upon detecting said control valve failure.  automatically detecting failure of one of said control valves which passes steamflow therethrough at a flowrate below a demand flowrate provided by one of said pressure regulator and said turbine controller; and  automatically opening said bypass valve upon detecting said control valve failure. 2. A system according to claim 1 further comprising: 3. A system according to claim 2 further comprising for each of said control valves: 4. A system according to claim 2 further comprising a pressure sensor joined to said turbine for providing a pressure signal for said main steam inside said turbine; and 5. A system according to claim 2 further comprising an electrical power sensor joined to said generator for providing an electrical power signal from said generator; and 6. A system according to claim 2 further comprising a plurality of flow sensors each joined in serial flow communication between a respective one of said control valves and said turbine for providing an actual flow signal for said main steamflow through said control valves; and 7. A system according to claim 6 further including a recirculation flow control system (RFCS) operatively joined to said reactor for selectively varying recirculation flow of said water in said reactor for controlling flowrate of said main steam therefrom; 8. A system according to claim 6 further including a control rod positionable in said reactor by a control rod drive and controlled by a rod control system, and said failure detection means are operatively joined to said rod control system and effective for inserting said control rod into said reactor for reducing power to reduce said main steamflow. 9. A system according to claim 8 wherein said failure detecting means are effective for providing a reduction demand to said RFCS for reducing said main steamflow from said reactor in a reduction value attributed to a maximum, normal contribution of a single one of said control valves. 10. A method of operating a nuclear reactor joined in flow communication with a steam turbine by a main steamline having a plurality of control valves for controlling main steamflow to said turbine, and bypass valve for selectively bypassing a portion of said main steamflow around said control valves and said turbine to a condenser, said control valves and bypass valve being controlled by a pressure regulator and a turbine controller; said method including the steps of: 11. A method according to claim 10 further including the step of automatically reducing power in said reactor to reduce said main steamflow to cause said open bypass valve to close.