Patent Number: 
Section: description

The present invention relates to a nuclear reactor power regulator that can automatically regulate reactor power from a plant shutdown (stop) state to a rated reactor power. Reactor power regulators have been developed for nuclear power plants in which thermal energy of steam generated by a reactor or a steam generator provided independently of the reactor is converted into electrical energy by a turbine and a power generator, the apparatuses being intended to regulate a reactor output (power) in a range from a plant stop state to a rated power generator output at the time of plant activation and stop or in a daily load following operation that deals with electric power load fluctuations during daytime and nighttime. Examples of the conventional reactor power regulators are illustrated in FIGS. 8 and 9. In the conventional nuclear reactor power regulator as a first configuration example illustrated in FIG. 8, a central load dispatching center 1 or an operator 2 inputs an operation pattern (signal) 101 to an interface device 3. The interface device 3 inputs a reactor output target value (signal) 102 (which will be simply referred to as “target value 102”, hereinafter) and a reactor output change rate (signal) 103 (which will be simply referred to as “change rate 103”, hereinafter) to a reactor output controlling device 4 in accordance with the operation pattern 101. Instead of the operation pattern 101, the central load dispatching center 1 or the operator 2 can also input the target value 102 and the change rate 103 directly to the interface device 3. The reactor output controlling device 4 calculates a reactor output control signal 108 (which will be simply referred to as “signal 108”, hereinafter) using the target value 102, the change rate 103, and a reactor output equivalent signal 106 (which will be simply referred to as “equivalent signal 106”, hereinafter). The reactor output controlling device 4 calculates the signal 108 according to, for example, the following method. The signal 108 is calculated as a signal for controlling the reactor to a reactor output set value 118 (which will be simply referred to as “set value 118”, hereinafter). (1) The set value 118 is calculated in accordance with the change rate 103, from a power generator output 106a corresponding to the reactor output equivalent signal 106 at the time of control start. The calculation is performed by a reactor output setting element 41 of the reactor output controlling device 4 until the set value 118 reaches the target value 102. (2) After the power generator output (signal) 106a and a deviation 118a between the power generator output 106a and the set value 118 calculated by the reactor output setting element 41 are input to a controlling element 42, the controlling element 42 calculates the signal 108. The calculation is performed until a deviation between the set value (signal) 118 and the equivalent signal 106 is eliminated. A deviation between a pressure controller output signal and the signal 108 may be used to calculate the signal 108, as needed. Here, the pressure control output signal is calculated based on a deviation between a main steam pressure signal and a main steam pressure set value (signal). A reactor output controller 7 actuates a reactor output controlling equipment 8 by using the signal 108. For example, in a case of a boiling water reactor, a recirculation flow controlling unit included in the reactor output controller 7 outputs a reactor output controlling equipment actuation request signal 109 (which will be simply referred to as “signal 109”, hereinafter) using the signal 108, to thereby change a drive state of a reactor recirculation pump 8a included in the reactor output controlling equipment 8 and thus changes a recirculation flow (flow rate). A reactor output, a main steam flow (flow rate), and the power generator output 106a change along with the change of the recirculation flow. The signal 108 is continuously output by the reactor output controlling device 4 until the deviation between the power generator output 106a and the set value 118 is eliminated, whereby the reactor output can be regulated to the target value. Conventionally, in a normal operation, nuclear power plants are operated so that the power generator output is a rated value (100%). The reactor output at the time of the rated power generator output is different depending on cooling water temperature for cooling a condenser of a steam turbine. In seasons in which the cooling water temperature is low, power generation efficiency is high, and hence the reactor output is set to be lower so that the rated power generator output is maintained. Meanwhile, in an operation that tends to be adopted more and more in recent years, a larger amount of electric power is output while the reactor output is maintained at a rated reactor power. In this case, a value generally adopted as the reactor output is a reactor output signal calculated by a reactor output calculating device. The reactor output calculating device performs computation based on a thermal equilibrium from various necessary plant state quantities for each predetermined period of time. Accordingly, development of nuclear reactor power regulator that uses the following signals as the equivalent signal 106 instead of the power generator output 106a to thereby automatically perform a rated reactor power (output) constant operation has been started as described in Patent Document 1 (see FIG. 9). That is, in the conventional nuclear reactor power regulator as a second configuration example illustrated in FIG. 9, the conventional nuclear reactor power regulator as the second configuration example uses: (A) a reactor output signal 105 (which will be simply referred to as “signal 105”, hereinafter) calculated by a reactor output calculating device 5 that performs computation based on a thermal equilibrium from various necessary plant state quantities (parameters) 104; (B) a signal 206b obtained by correcting and converting an APRM signal 106b in a neutron instrumentation system of the reactor, using a conversion factor set in consideration of degradation over time of a detector and the like; and (C) a signal 206a obtained by correcting and converting the power generator output 106a using efficiency that depends on a degree of condenser vacuum and the like, as the equivalent signal 106 instead of the power generator output 106a.  Unfortunately, in a case where control is performed using a power generator output signal and the like in the conventional nuclear reactor power regulator, even if a deviation from the signal 105 occurs, it is difficult to eliminate the deviation. In consideration of above-mentioned circumstance, at present, the nuclear reactor power regulation (adjustment) from a rated power generator output to a rated reactor power and a rated reactor power constant operation are manually performed.      Patent Document 1: Publication of (Unexamined) Japanese Patent Application No. Showa 64-218996  A technique of automatically performing a reactor power regulation operation at the time of activation and stop or in a daily load following operation has been developed for the conventional nuclear reactor power regulators described in Background Art. The conventional nuclear reactor power regulators that have been developed up to now are capable of automation of a reactor power regulation operation from a plant stop state to a rated power generator output, but have the following problems 1 and 2 in order to achieve an automatic increase in output up to a rated reactor power. Accordingly, automation of an output operation from the rated power generator output to the rated reactor power is difficult for the conventional apparatuses, and hence the output operation is manually performed little by little. Further, the rated reactor power is manually maintained due to the same problems as the following problems 1 and 2. 1. In the conventional nuclear reactor power regulator illustrated in FIG. 9, a calculation interval in a process calculator of the reactor output calculating device 5 is normally a several-minute interval, and hence a time delay of several minutes occurs in the signal 105. Accordingly, the apparatus cannot deal with a transient change that occurs in a time shorter than the calculation interval in the reactor output calculating device 5, and the signal 105 calculated by the reactor output calculating device 5 cannot be used for output control as it is. 2. In the conventional nuclear reactor power regulator illustrated in FIG. 9, in a case where control is performed using: the signal 206b obtained by correcting, by a conversion device 13b, the APRM signal 106b in the neutron instrumentation system of the reactor in consideration of degradation over time and the like; or the signal 206a obtained by correcting, by a conversion device 13a, the power generator output 106a using the efficiency that depends on the degree of condenser vacuum and the like, even if a deviation from the signal 105 calculated by the reactor output calculating device 5 occurs, the deviation cannot be eliminated, and the rated reactor power cannot be maintained. Even if the signals in the problems 1 and 2 are switchingly used for the sake of controlling or maintaining a reactor output operation, the problems cannot be solved. The problems occur because the signal 105 cannot be obtained as a continuous signal in spite of the fact that the reactor output is generally defined as the signal 105 calculated by the reactor output calculating device 5. That is, in order to solve the problems 1 and 2, it is necessary to obtain a continuous signal being equivalent to the signal 105 even if a calculation interval of the signal 105 is intermittent. If the continuous signal being equivalent to the signal 105 is obtained, automation of stable reactor power regulation from the plant shutdown (stop) state to the rated reactor power is expected to be achieved. In view of this, in order to provide a function of obtaining a continuous signal (reactor output equivalent signal) being equivalent to the signal 105 even if the calculation interval of the signal 105 is intermittent, how to configure the nuclear reactor power regulator is important. The present invention, which has been made in view of the above-mentioned circumstances, has an object to provide a nuclear reactor power regulator having a function of obtaining a signal equivalent to a continuous reactor output signal regardless of a calculation interval of the reactor output signal, the nuclear reactor power regulator being capable of automation of stable reactor power regulation from a plant shutdown (stop) state to a rated reactor power. In order to achieve the above-mentioned object, a nuclear reactor power regulator according to an embodiment of the present invention, the nuclear reactor power regulator regulating an output of a reactor on a basis of an operation pattern or a reactor output target value and a reactor output change rate that are input by a central load dispatching center or an operator, including: a reactor output calculating device that performs computation based on a thermal equilibrium from various necessary plant state quantities to calculate a reactor output signal; a correcting device that corrects a continuously obtained reactor output equivalent signal that is considered to be equivalent to a reactor output at a calculation interval of the reactor output signal, for each calculation interval in the reactor output calculating device so that the reactor output equivalent signal coincides with the reactor output signal calculated by the reactor output calculating device, and calculates a continuous corrected reactor output equivalent signal; a reactor output controlling device that calculates at least one type of reactor output control signal for controlling the output of the reactor, using the corrected reactor output equivalent signal, the reactor output target value, and the reactor output change rate; and a reactor output controller that is actuated on a basis of the reactor output control signal. According to the present invention, stable reactor power regulation from a plant stop state to a rated reactor power can be automated. Hereinafter, nuclear reactor power regulators according to embodiments of the present invention are described with reference to the drawings.  FIG. 1 is a configuration diagram illustrating a nuclear reactor power regulator 30 that is an example nuclear reactor power regulator according to a first embodiment of the present invention. The nuclear reactor power regulator 30 includes: an interface device 3 that outputs a reactor output target value (signal) 102 (which will be simply referred to as “target value 102”, hereinafter) and a reactor output change rate (signal) 103 (which will be simply referred to as “change rate 103”, hereinafter) using an operation pattern (signal) 101 or the target value 102 and the change rate 103 that are input by a central load dispatching center 1 or an operator 2; a reactor output controlling device 4 that outputs a reactor output control signal 108 (which will be simply referred to as “signal 108”, hereinafter) using the target value 102, the change rate 103, and a corrected reactor output equivalent signal 107 (which will be simply referred to as “corrected equivalent signal 107”, hereinafter); a reactor output controller 7 that calculates a reactor output controlling equipment actuation request signal 109 (which will be simply referred to as “signal 109”, hereinafter) using the signal 108; a reactor output calculating device 5 that performs computation based on a thermal equilibrium from various necessary plant state quantities (signals) 104 to calculate a signal 105; and a correcting device 6 that outputs the corrected equivalent signal 107 to the reactor output controlling device 4 and the interface device 3, the corrected equivalent signal 107 being calculated by correcting a reactor output equivalent signal 106 (which will be simply referred to as “equivalent signal 106”, hereinafter) that is continuously obtained and considered to be equivalent to a reactor output at a calculation interval of the reactor output, using the calculated signal 105. The reactor output controlling device 4 includes a first reactor output controlling unit 4a including a reactor output setting element 41 and a controlling element 42. The reactor output controlling device 4 (first reactor output controlling unit 4a) calculates the signal 108 according to, for example, the following method. The signal 108 is calculated as a signal for controlling the reactor to a reactor output set value 118 (which will be simply referred to as “set value 118”, hereinafter). (1) The set value (signal) 118 is calculated in accordance with the change rate 103, from the corrected equivalent signal 107 at the time of control start. The calculation is performed by the reactor output setting element 41 of the reactor output controlling device 4 until the set value 118 reaches the target value 102. (2) The corrected equivalent signal 107 and a deviation 118a between the corrected equivalent signal 107 and the set value 118 are input to the controlling element 42 of the reactor output controlling device 4, and the signal 108 is calculated. This calculation is performed until the deviation between the set value 118 and the corrected equivalent signal 107 is eliminated. A deviation between a pressure controller output signal and the signal 108 may be used to calculate the signal 108, as needed. The pressure controller output signal is calculated from a deviation between a main steam pressure signal and a main steam pressure set value. Here, a signal selected as the equivalent signal 106 may be a continuously obtained signal correlated with the reactor output at the calculation interval in the reactor output calculating device 5. Examples of the continuously obtained signal correlated with the reactor output at the calculation interval in the reactor output calculating device 5 include a total flow detection signal 106c, an in-reactor neutron flux signal 106b, a power generator output signal 106a, and so on. The reactor output controller 7 actuates a reactor output controlling equipment 8 by using the signal 108. For example, in a case of a boiling water reactor, a recirculation flow controlling unit 7a serving as the reactor output controller 7 outputs the signal 109 using the signal 108, to thereby change a drive state of a reactor recirculation pump 8a serving as the reactor output controlling equipment 8 and thus change a recirculation flow (flow rate). If the recirculation flow is changed, the reactor output and a main steam flow (flow rate) and a power generator output corresponding to the signals 106 change along with the change of the recirculation flow. The signal 108 is continuously output by the reactor output controlling device 4 until the deviation between the set value 118 and the corrected equivalent signal 107 calculated using the signals 106 is eliminated, whereby the reactor output can be regulated to the target value. Incidentally, although the nuclear reactor power regulator 30 illustrated in FIG. 1 includes the recirculation flow controlling unit 7a as the reactor output controller 7, another reactor output controller may be used as the reactor output controller 7. An example of the reactor output controller may be used as the reactor output controller 7 includes a control rod position controlling unit instead of the recirculation flow controlling unit 7a, the reactor output controlling unit regulating the reactor output by controlling a position of a control rod. In the nuclear reactor power regulator 30 illustrated in FIG. 1, the interface device 3, the reactor output controlling device 4, the reactor output calculating device 5, the correcting device 6, the reactor output controller 7, and the reactor output controlling equipment 8 included in the nuclear reactor power regulator 30 are each configured in a simplex manner. As another example of the nuclear reactor power regulator 30, alternatively, at least any of the interface device 3, the reactor output controlling device 4, the reactor output calculating device 5, the correcting device 6, the reactor output controller 7, and the reactor output controlling equipment 8 is configured in a multiplex manner. In this example of the nuclear reactor power regulator 30 as well as the nuclear reactor power regulator 30 illustrated in FIG. 1 can adjust the reactor output. The following correction methods are given as a calculation example of the corrected equivalent signal 107 by the correcting device 6. <Correction Method 1> A method of multiplying the equivalent signal 106 by correction gain G1corrected equivalent signal 107=correction gain G1×equivalent signal 106  (S1) The correction gain G1 serves to adjust so that the corrected equivalent signal 107 and the signal 105 are coincided with each other for each calculation interval in the reactor output calculating device 5.correction gain G1=signal 105/equivalent signal 106   (S2) <Correction Method 2> A method of adding the signal 105 to a product obtained by multiplying a difference between the equivalent signal 106 and the signal 105 by gain.corrected equivalent signal 107=signal 105+FG(equivalent signal 106)×(equivalent signal 106−signal 105)   (S3) In the formula (S3), FG(X) represents a function for giving gain corresponding to a value of X, the function being set in advance so that the corrected equivalent signal 107 and the signal 105 coincide with each other. The signal 105 is updated for each calculation interval in the reactor output calculating device 5. <Correction Method 3> A method of multiplying a function for converting so that the equivalent signal 106 coincides with the signal 105, by correction gain G2corrected equivalent signal 107=correction gain G2×FS(equivalent signal 106)  (S4) In the formula (S4), FS(X) is a function that is set in advance so that the corrected equivalent signal 107 and the signal 105 coincide with each other. In order to correct a deviation between a preset value and an actually measured value, the correction gain G2 is adjusted (regulated) in the following manner for each calculation interval in the reactor output calculating device 5.correction gain G2=signal 105/FS(equivalent signal 106)  (S5) <Correction Method 4> A method of adding correction bias B to a function for converting so that the equivalent signal 106 coincides with the signal 105corrected equivalent signal 107=FS(equivalent signal 106)+B  (S6) In the formula (S6), FS(X) is a function that is set in advance so that the corrected equivalent signal 107 and the signal 105 coincide with each other. In order to correct a deviation between a preset value and an actually measured value, the correction bias B is adjusted in the following manner for each calculation interval in the reactor output calculating device 5.correction bias B=signal 105−FS(equivalent signal 106)   (S7) No matter which of the correction methods 1 to 4 is used, the correcting device 6 can make such correction that the equivalent signal 106 coincides with the signal 105, for each calculation interval in the reactor output calculating device 5, whereby the deviation from the signal 105 can be suppressed within a predetermined range. Further, the correcting device 6 can calculate a signal (corrected equivalent signal 107) equivalent to a continuous reactor output signal that is considered to be equivalent to the reactor output at the calculation interval of the reactor output signal. Therefore, in the nuclear reactor power regulator 30, even if the calculation interval of the reactor output signal is intermittent, the corrected equivalent signal 107 can be obtained regardless of the calculation interval of the reactor output signal. The corrected equivalent signal 107 is a signal being equivalent to a continuous reactor output signal that is considered to be equivalent to the reactor output at the calculation interval, of which deviation from the signal 105 is suppressed within a predetermined range. The nuclear reactor power regulator 30 can obtain the corrected equivalent signal 107, and therefore suppress occurrence of the deviation between the corrected equivalent signal 107 and the signal 105. If the corrected equivalent signal 107 is output to the interface device 3, the corrected equivalent signal 107 can be monitored on a display element of the interface device 3. As a result, the operator 2 can always monitor a value of the corrected equivalent signal 107 through the interface device 3. There is an example of the corrected reactor output equivalent signal 107 obtained by the nuclear reactor power regulator 30 in FIG. 2. As illustrated in FIG. 2, since the signal 105 calculated by the reactor output calculating device 5 is an intermittent signal, the signal 105 cannot be used as the reactor output control signal as it is. Further, even if a deviation from a reactor output P occurs in the equivalent signal 106, the deviation cannot be immediately resolved, and hence the equivalent signal 106 cannot adjust the reactor output to the target reactor output P. Meanwhile, in the nuclear reactor power regulator 30, the corrected equivalent signal 107 equivalent to the continuous signal 105 can be obtained. Although a deviation may occur in the corrected equivalent signal 107 if the change rate 103 is high, the deviation of the corrected equivalent signal 107 can be suppressed to be smaller than that of the equivalent signal 106. In the nuclear reactor power regulator 30, the signal 108 is continuously output until the deviation between the corrected equivalent signal 107 and the target value 102 or the set value 118 becomes zero, and reactor output control is performed, whereby reactor power regulation up to a rated reactor power, which has been conventionally manually performed, can be automatically performed. There is an example activation curve of the nuclear reactor power regulator 30 in FIG. 3. The nuclear reactor power regulator 30 of the present embodiment is capable of the automatic control up to the rated reactor power, and can thereby make it unnecessary that the operator 2 performs mode switching (switching from an automatic mode to a manual mode) in reactor power regulation at a rated power generator output, which has been conventionally necessary. Accordingly, the reactor power regulation is possible in a shorter time with a reduced burden on the operator 2 in a state where the reactor power regulation up to the rated reactor power is automated.  FIG. 7 is a configuration diagram illustrating a nuclear reactor power regulator 30D that is an example nuclear reactor power regulator according to a fifth embodiment of the present invention. In describing the nuclear reactor power regulator 30D, the same configurations as those in the nuclear reactor power regulator 30 are denoted by the same reference numerals or characters, and redundant description thereof is omitted. The nuclear reactor power regulator 30D is basically different in configuration from the nuclear reactor power regulator 30 in that the nuclear reactor power regulator 30D further includes: an automation on/off switching device 25 that switches an on/off state of the automation of the reactor power regulation, that is, makes switching between an automatic mode (on) in which the reactor power regulation is automatically performed and a manual mode (off) in which the reactor power regulation is manually (non-automatically) performed; and an automation cancellation signal generating device 26 that requests the switching device 25 to switch on or off the automation of the reactor power regulation. The nuclear reactor power regulator 30D illustrated in FIG. 7 includes a plurality of the switching devices 25 (25a, 25b). The first switching device 25a disconnects the target value 102 and the change rate 103 from the reactor output controlling device 4. Since the nuclear reactor power regulator 30D includes the first switching device 25a, the nuclear reactor power regulator 30D enables a set value to follow the corrected equivalent signal 107 received from the correcting device 6, whereby the reactor output is maintained. The second switching device 25b disconnects the signal 108 received from the reactor output controlling device 4 from the reactor output controller 7, as needed, for example, in a case where the corrected equivalent signal 107 is lost. Since the nuclear reactor power regulator 30D includes the second switching device 25b, the nuclear reactor power regulator 30D can prevent the reactor output control from being performed using an erroneous signal. Accordingly, during the reactor output control using the corrected equivalent signal 107, the nuclear reactor power regulator 30D can always cancel the automation of the reactor output control as needed, and can prevent unexpected reactor output control from being performed. Further, if the nuclear reactor power regulator 30D further includes the automation cancellation signal generating device 26, the switching by the switching device 25 can be automated. The signal 105 or the corrected equivalent signal 107 is input to the automation cancellation signal generating device 26. Then, in a case where any of the two signals exceeds the rated reactor power by a given value or more, an automation cancellation signal 116 is transmitted to the switching device 25, and the automation of the reactor output control is cancelled. In a case of using the nuclear reactor power regulating method described in any of the nuclear reactor power regulators (the nuclear reactor power regulators 30 to 30C) of the first embodiment to the fourth embodiment, it is considered that the reactor output cannot normally exceed the rated reactor power. However, if the reactor output exceeds the rated reactor power by a given value or more, the nuclear reactor power regulator 30D can automatically cancel the automated operation, and can thereby prevent the operation in a region beyond the rated reactor power. In another method, in a case where the reactor output control cannot be performed due to a malfunction of the reactor output controller 7, a reactor output controller malfunction signal 119 is input from the reactor output controller 7 to the automation cancellation signal generating device 26. Then, the automation cancellation signal generating device 26 generates the automation cancellation signal 116 and outputs to the switching device 25, whereby the automated operation may be cancelled. In a case where the automation is cancelled, an automation cancellation information signal 117 is output to the interface device 3, whereby the cancellation is reported to the operator 2. Accordingly, the operator 2 can always monitor whether or not the reactor output control is automated (whether or not the automation is cancelled), on the display (monitor) of the interface device 3. Although some embodiments of the present invention were described, these embodiments are in all respects illustrative and are not considered as the basis for restrictive interpretation. These new embodiments can be performed in other various forms, and various kinds of removals, replacements and modifications are possible without departing from the meaning of the present invention. These embodiments and their modifications are intended to be embraced in the range and meaning of the present invention, and are particularly intended to be embraced in the invention disclosed in the range of the claims and the equivalency thereof.                    1 - - - CENTRAL LOAD DISPATCHING CENTER        2 - - - OPERATOR        3 - - - INTERFACE DEVICE        4 (4a), 14 (4a, 4b) - - - REACTOR OUTPUT CONTROLLING DEVICE        5 - - - REACTOR OUTPUT CALCULATING DEVICE        6, 6a, 6b - - - CORRECTING DEVICE        7 - - - REACTOR OUTPUT CONTROLLER        7a - - - RECIRCULATION FLOW RATE CONTROLLING UNIT        8 - - - REACTOR OUTPUT CONTROLLING MACHINE        8a - - - REACTOR RECIRCULATION PUMP        9 - - - REACTOR        10 - - - MAIN STEAM PIPE        11 - - - TURBINE        12 - - - GENERATOR        13a, 13b - - - CONVERSION DEVICE        15 - - - REACTOR OUTPUT CONTROL SIGNAL SWITCHING DEVICE        16 - - - SIGNAL SWITCHING CONTROLLER        17 - - - REACTOR OUTPUT CHANGE RATE SUPPRESSION DEVICE        20 - - - REACTOR OUTPUT EQUIVALENT SIGNAL SWITCHING DEVICE        21 - - - SIGNAL SWITCHING CONTROLLER        22 - - - CORRECTED REACTOR OUTPUT EQUIVALENT SIGNAL SWITCHING DEVICE        25 (25a, 25b) - - - AUTOMATION ON/OFF SWITCHING DEVICE        26 - - - AUTOMATION CANCELLATION SIGNAL GENERATING DEVICE        30, 30A, 30B, 30C, 30D - - - REACTOR OUTPUT ADJUSTING APPARATUS        101 - - - OPERATION PATTERN        102 - - - REACTOR OUTPUT TARGET VALUE        103 - - - REACTOR OUTPUT CHANGE RATE        104 - - - PLANT STATE QUANTITIES (PARAMETERS)        105 - - - REACTOR OUTPUT SIGNAL        106 - - - REACTOR OUTPUT EQUIVALENT SIGNAL        106a - - - POWER GENERATOR OUTPUT SIGNAL        106b - - - IN-REACTOR NEUTRON FLUX SIGNAL        106c - - - TOTAL FLOW RATE DETECTION SIGNAL        107 - - - CORRECTED REACTOR OUTPUT EQUIVALENT SIGNAL        108 - - - REACTOR OUTPUT CONTROL SIGNAL        108a - - - FIRST REACTOR OUTPUT CONTROL SIGNAL        108b - - - SECOND REACTOR OUTPUT CONTROL SIGNAL        109 - - - REACTOR OUTPUT CONTROLLING EQUIPMENT ACTUATION REQUEST SIGNAL        110 - - - REACTOR OUTPUT CONTROL SIGNAL SWITCHING REQUEST SIGNAL        111 - - - REACTOR OUTPUT CONTROL SIGNAL SWITCHING SIGNAL        112 - - - REACTOR OUTPUT CHANGE RATE SUPPRESSION SIGNAL        113 - - - CORRECTED REACTOR OUTPUT EQUIVALENT SIGNAL BEFORE-AFTER-CORRECTION DEVIATION SIGNAL        114 - - - REACTOR OUTPUT EQUIVALENT SIGNAL/CORRECTED REACTOR OUTPUT EQUIVALENT SIGNAL SWITCHING REQUEST SIGNAL        115 - - - REACTOR OUTPUT EQUIVALENT SIGNAL/CORRECTED REACTOR OUTPUT EQUIVALENT SIGNAL SWITCHING SIGNAL        116 - - - AUTOMATION CANCELLATION SIGNAL        117 - - - AUTOMATION CANCELLATION ANNUNCIATION SIGNAL        118 - - - REACTOR OUTPUT SET VALUE        119 - - - REACTOR OUTPUT CONTROLLER MALFUNCTION SIGNAL