Patent Number: 
Section: claims

1. A method of operating a Boiling Water Reactor, said boiling water reactor having fuel assemblies arranged inside of channels through which coolant flows, comprising:a step of analyzing Local Power Range Monitor signals for oscillatory behavior indicative of neutron flux coupled density wave oscillations;determining if oscillatory behavior beyond a noise level is present in the signals;initiating a first reactor protective corrective action if the oscillatory behavior is determined to be present;if the Local Power Range Monitor signals analyzed in the step of analyzing Local Power Range Monitor signals are not oscillatory beyond noise level, a step of analyzing several channels of high power using a stability program on line at actual operating conditions and checking to determine if neutron flux uncoupled oscillations are possible; andinitiating a second reactor protective corrective action while the Local Power Range Monitor signals are not oscillatory beyond noise level if it is determined in the step of analyzing several channels of high power that neutron flux uncoupled oscillations are possible; andrepeating at least the step of analyzing Local Power Range Monitor signals if it is determined in the step of analyzing several channels of high power that neutron flux uncoupled oscillations are not possible. 2. The method according to claim 1, wherein at least one of the first step and the second step of initiating a reactor protective corrective action is scramming the reactor. 3. The method according to claim 1, wherein at least one of the first step and the second step of initiating a reactor protective corrective action is reducing reactor power. 4. The method according to claim 1, wherein the step of analyzing several channels of high power using a stability program on-line at actual operating conditions and checking to determine if neutron flux uncoupled oscillations are possible is performed by use of on-line computer simulations. 5. A method of operating a Boiling Water Reactor designed for power generation, said boiling water reactor having fuel assemblies arranged inside of channels through which coolant flows, said method comprising the steps of:analyzing Local Power Range Monitor signals for oscillatory behavior indicative of neutron flux coupled density wave oscillations;determining if oscillatory behavior is present in the signals;initiating a first reactor protective corrective action if the oscillatory behavior is determined to be present; and,if the Local Power Range Monitor signals analyzed in the step of analyzing Local Power Range Monitor signals are not oscillatory beyond noise levels of said Local Power Range Monitor signals, performing the further steps of:determining the identity of a plurality of channels which are operating at a relatively high power as compared to other channels;analyzing the plurality of channels which are operating at a relatively high power using a stability program on-line at actual operating conditions and checking to determine if neutron flux uncoupled oscillations are possible;initiating a second reactor protective corrective action while the Local Power Range Monitor signals are not oscillatory beyond noise levels if it is determined in the step of analyzing the plurality of channels which are operating at a relatively high power that neutron flux uncoupled oscillations are possible; andrepeating at least the step of analyzing Local Power Range Monitor signals if it is determined in the step of analyzing the plurality of channels which are operating at a relatively high power that neutron flux uncoupled oscillations are not possible. 6. The method according to claim 5, wherein at least one of the first step and the second step of initiating a reactor protective corrective action is scramming the reactor. 7. The method according to claim 5, wherein at least one of the first step and the second step of initiating a reactor protective corrective action is reducing reactor power. 8. The method according to claim 5, wherein the step of analyzing the plurality of channels which are operating at a relatively high power using a stability program on-line at actual operating conditions and checking to determine if neutron flux uncoupled oscillations are possible is performed by use of on-line computer simulations. 9. The method according to claim 5, wherein the actual operating conditions comprise a channel operating condition selected from the group consisting of: power, axial power profile, coolant flow rate, inlet flow temperature, and system pressure. 10. The method according to claim 5, wherein the actual operating conditions comprise operating power and coolant flow. 11. The method according to claim 1, wherein the actual operating conditions comprise a channel operating condition selected from the group consisting of: power, axial power profile, coolant flow rate, inlet flow temperature, and system pressure. 12. The method according to claim 1, wherein the actual operating conditions comprise operating power and coolant flow.