JPS6298102A - Feedwater controller for steam generating plant - Google Patents

Abstract

(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a water supply control device for a steam generation plant, and particularly to a water supply control device for a steam generation plant suitable for application to a boiling water type atomic coupler plant.

[Conventional technology]

A conventional water supply control device for a boiling water type atomic couplant is shown in FIG. 1 on page 16 of Japanese Patent Application Laid-Open No. 197499/1983. The water supply control device supplies water to the reactor pressure vessel of a boiling water nuclear coupler plant, which is a type of steam generator. Two turbine-driven water pumps (hereinafter abbreviated as TD-FLFP) and electric lj
Controls two motor-driven water pumps (hereinafter abbreviated as MD-RFP) with a capacity of 25% driven by machine h. M
DR, FP is a reactor startup in which steam generated in the reactor pressure vessel cannot be used.

It is used when the TD-RFP is stopped or as a backup when the TD-RFP is stopped. Therefore, during normal operation, two TD-RFPs are operated.

The feed water controller takes in the water level in the reactor pressure vessel (hereinafter referred to as reactor water level), the feed water flow rate, and the values of the main steam flow rate and controls the feed water flow rate supplied to the reactor pressure vessel. Keep the water level at a specified level.

Adjustment of the water supply flow rate discharged from TD-RFP is performed using TD-RFP.
The opening degree of the steam control valve that controls the steam supplied to the driving turbine of the RFP is set to 1. This is done by adjusting according to the drive turbine rotation speed request signal output from the water supply controller.

On the other hand, since the MD-RFP is driven by an electric motor rotating at a constant speed, the opening degree of the water supply regulating valve provided on the discharge side of the MD-RFP is determined by the valve opening degree request signal 10 output from the water supply control device.
and 11 to adjust the water supply flow rate.

When an abnormality is detected and the water pump needs to be tripped, the water pump trip device trips the water pump. That is, the TD-RFP trips when the water supply pump trip device suddenly closes the steam stop valve provided upstream of the steam control valve (steam flow i control valve). Further, the MD-RFP is tripped by opening the circuit breaker of the drive motor using a water supply pump trip device. Causes of water supply pot trips include condensate pump stoppage, TD-R, FP suction pressure low,
An example of this is an abnormal signal from the plant side due to high reactor water level.

If either of these signals is output, the control oil of the steam stop valve is removed and the steam stop valve is suddenly closed. With the closure of this valve, the supply of steam to the drive turbine is cut off, and the TD-F
LFP stops.

Next, we will explain the behavior of the atomic couplant of boiling water when the water supply tube trips for some reason.

(1) If one of the TD-RF P units trips while two units are in operation, TD-1'tWhen the FPI unit trips, a drop in the control oil pressure of the pump drive turbine steam stop valve is detected and the TD-RF
It is determined that P has tripped, and the two units □~fD-nPP are immediately activated fully automatically by the water supply system Ie. By the way,
If MD-RF"P does not start automatically, the speed of the recirculation pump that supplies cooling water to the reactor core will be reduced by 172 when the reactor water level drops to a certain set value (hereinafter, the recirculation pump speed will be reduced by 172%. This reduces the reactor output and suppresses the generation of steam.

This makes it possible to avoid a reactor scram due to a drop in reactor water level.

(2) If one TD-4FP trips while its pump is in operation, two ML")-RFr' are automatically activated to suppress the drop in the reactor water level, as in the case of (]).

(If a pump trip occurs while the 3MD-RFPI unit is in operation, the stopped MD-RFP automatically starts and the tripped MD
- Supplement the water supply that RFP was responsible for and suppress the drop in reactor water level.

[Problem that the invention seeks to solve]

As a result of detailed study of the functions of conventional water supply control devices, the inventors found that an abnormality occurred in the hydraulic system (e.g., servo valve and servo motor) that controls the steam control valve by inputting the output signal of the turbine control device. To.

It has been found that the steam control valve (steam flow rate control valve) may close regardless of the control signal output from the turbine control device. In such a case, the steam supplied to the driving steam turbine is lost and the turbine rotational speed rapidly decreases.

However, since the water pump trip signal does not occur (
(The steam stop valve is not closed), MD-R and FP are also not automatically started. the result.

As shown in Figure 5, the water supply pump flow rate decreases, and the total water supply flow 1
Since the reactor water level and pressure also drop, the reactor scram may occur due to the low pressure of the reactor water level. The characteristics shown in FIG. 5 are obtained when the steam control valve that adjusts the amount of steam supplied to one of the two TD-RFPs in operation is closed as described above.

Also, when the MD-R or FPI unit is in operation, the water supply regulating valve (water supply flow rate regulating valve) may close due to a failure of the electro-pneumatic converter, etc. that converts the control signal output from the water supply control device into air pressure. The above study also revealed that there is a possibility that the discharge flow rate of D-RFP may be lost if the drive motor breaker of MD-RFP does not open.In this case, the 1VD-RFP trip signal If this does not occur,
The other MD-RF'P will not start automatically,
Similar to the hydraulic system failure at TO-RFI' mentioned above, a reactor scram occurs due to the low reactor water level. Note that the steam control valve and water supply control valve have a flow rate of 1 iJl (control valves).

SUMMARY OF THE INVENTION An object of the present invention is to provide a water supply control device for a steam generation plant that can prevent a steam generator from shutting down due to closure of a flow control valve while a water supply pump is being driven.

[Failure to solve the problem]

The above-mentioned problems are caused by installing means to detect the feed water flow rate, main steam flow rate, and reactor water level, and there is an abnormality in the deviation between the measured value of the feed water flow rate and the measured value of the main steam flow rate, and the measured atom This problem is solved by providing a control means that starts the motor-driven water pump when the reactor water level is abnormal.

In addition, means are provided to detect the number of revolutions of the water supply pump, the driving turbine, and the opening degree of the steam control valve provided in the steam piping for driving the turbine. This problem is solved by providing a control means for tripping the turbine-driven water supply pump when both the valve opening signals are different and the above-mentioned control means outputs a starting signal for the seven-way drive water supply pump. .

[Effect]

MD-RFP is activated when the measured value of the feed water flow rate and the measured value of the main steam flow rate are different from each other, so it is possible to suppress the decrease in the water level in the steam generator and prevent the steam generator from shutting down. can.

It also detects abnormalities in the rotational speed of the driving turbine of TD-RF'P and abnormalities in the opening degree of the steam control valve.

Due to the abnormality of both, T D-R, FP, 1:)
') Since the trip activates the MD-RFP, it is possible to suppress the decrease in the water level in the steam generator and prevent the steam generator from shutting down.

Also, as a trip signal for TD-RFP.

By using a combination signal of two signals: TD-R, FP drive turbine rotation speed and steam control valve opening, it is possible to prevent false trips when each individual trip signal is a false signal. .

〔Example〕

DESCRIPTION OF THE PREFERRED EMBODIMENTS A water supply control device for a steam generation plant, which is a preferred embodiment of the present invention applied to a boiling water type atomic coupler, will be described below with reference to FIGS. 1 and 2. The reactor pressure vessel of a boiling water nuclear coupler is a steam generator.

During normal operation of a boiling water type atomic coupler.

Cooling water (feed water) heated by the reactor core 2 in the reactor pressure vessel (steam generator) 1 turns into steam. This steam is discharged from the 1M slave reactor pressure vessel 1 and sent through the main steam pipe 2 to a turbine (not shown). Steam exhausted from the turbine is condensed into water in a condenser (not shown). The condensed water discharged from the condenser, in other words, the feed water that serves as cooling water for the reactor.

A condensate demineralizer (not shown) and a condensate pump (
(not shown) and a low pressure feedwater heater (not shown). Furthermore, the water supply is provided by branch pipes 3A and 3B of the water supply piping.
The water is pressurized by two TD-F'P4A and 4B installed in the reactor, heated by a high-pressure feed water heater, and supplied into the reactor pressure vessel 1.

Although not shown, there are two low pressure and high pressure feed water heaters.
The bleed steam from the main steam pipe 2 is connected to the heating source of the feed water. This extracted steam is condensed in each feed water heater,
It is led to the condenser as drain.

TD7RFP4A and 4B supply steam extracted from a turbine (not shown) through extraction pipes 6A and 6B to turbine 5A.
and 5B, respectively. These bleed steams are exhausted to a low pressure feed water heater (not shown). The rotation speed control of the TD-FP4A and 4B is performed by controlling the flow rate of the extracted steam supplied to the turbines 5A and 5B using the steam control valves 7 and 7 installed in the bleed pipes 6 and 6BK.
This is adjusted by opening and closing B. MD-RFPeA and 9B provided in branch pipes 3C and 3D of water supply pipe 3
During normal operation of the reactor, TD-FP 5A and 5
It is on standby as a backup for B. MD-RF
The PQA is driven during startup and shutdown of the reactor.

MD-RFP9B is also used as a backup for MD-RFPQA. The flow rate control of the water supply supplied by MD-RFPQA and 9B is performed by water supply adjustment valves (flow rate adjustment valves) 11 and 11B provided in branch pipes 3c and 3D. The water supply flow rate is controlled by the turbine steam control valves 7 and 7B and the water supply control valves 11A and IIBK by the water level gauge 12. which measures the water level in the reactor pressure vessel 1. Water distribution IW3
The measurement of the feed water flow meter 13 provided in the main steam pipe 2 and the main steam flow meter 14 provided in the main steam piping 2 is carried out by the feed water controller 15 which inputs the iilr.
JP-A-57-197499 No. 16@, M-RFP control device 36 shown in Fig. 1. It is composed of a function generator 549 and a turbine speed controller 48. In the above publication, the motor-driven water supply pump is referred to as M-RFP. It has a T'D-FP trip determination circuit 25 and a VID-FP trip determination circuit 28. The details of the logic of the water pump trip circuit 1G are illustrated in FIG. The details of the logic of the TD-F'P)1,1 tube determination circuit 250 are shown in FIG.

The Ml)-4FPl-rip determination circuit 28) logic is the same as the logic of the TD-RFP) rip determination circuit 25 shown in FIG. 3, with rTD-R and FPJ replaced by rMD-4PF'j.

In FIGS. 2 and 3, 24 and 26 are OR gates, 35, 43 . and 46 are AND gates, and 45 is AND and OR gates.

The water supply control system of this embodiment includes a water level gauge 12, a water supply flow meter 13, a main steam flow h1 meter 14, a water supply controller 15, a water supply pump trip circuit 16, a tachometer 29A, 29B, and an opening detector 30A. , 30B.

Tachometers 29A and 29B are attached to the rotating shafts of turbines 5 and 5B. These tachometers may be attached to the rotating shafts of the TD-RFP 4 persons and 4B, which are connected to the rotating shafts of the turbines 5 persons and 5B.

Opening degree detector 30 and 30B are the water supply adjustment valve 11. A and IIB.

During startup of the boiling water nuclear coupler, reactor pressure vessel 1
The control rods 32 inserted into the reactor core 2 are pulled out, and operations to raise the temperature and pressure inside the reactor pressure vessel 1 are performed. Water is supplied into the reactor pressure vessel 1 through a water supply pipe 3. As the reactor power increases, the water pump operation shifts to %MD-Rh'P two unit operation, TD-RF'PL unit operation, and TD-R, FPZ unit operation. During normal operation of the nuclear reactor, TD-RFP4A and 4B are operated. Control of the water supply flow rate in MD-RFP and TD-RFP is performed by water supply controller 15. That is, the three signals of the reactor water level, feed water flow rate, and steam flow rate detected by the feed water controller 15, the water level meter 12, the feed water flow meter 13, and the main steam flow meter 14, respectively, are input, and these three signals are TD-FLFP4 created by P, I operation of
The turbine rotation speed request signals S1 and S2 for the person and 4B are output. By inputting the steam control valves 7 and 7BFi, and their turbine rotational speed request signals 8+ and S2, the request signal S! and S2, the valve opening degree is adjusted. Therefore, the flow rate of water supplied to the TD-RFPs 4A and 4B is adjusted. The water supply controller 15 is.

When MD-FP9A or 9B is being driven.

Feed water regulating valves 11A and II output valve opening request signals S3 and S for the feed water regulating valves 11A and 11B obtained by PI calculation of the input reactor water level, feed water flow rate, and steam flow rate.
B adjusts the valve opening according to the input valve opening request signals S3 and S4. For this reason, MD-几FP9A and 9
The flow rate of water discharged from B is adjusted. By controlling the water supply flow rate by the water supply controller 15 in this way, the reactor water level is controlled to be constant.

In this embodiment, the water supply flow rate signal S output from the flow meter 13 is
14. Main steam flow rate signal S15 output from flow meter 14
．． Reactor water level signal output from water level gauge 12, turbine rotation speed signal 85 output from Slam tachometer 29 and 29B, and Sai turbine rotation speed request signals St and S2
．． Valve opening signal S? output from opening detectors 30A and 30B? and S8 are incorporated into the water supply pump trip circuit 16, and the trip determination circuit 17 is provided in the water supply pump) IJ tube circuit 16. By incorporating the trip determination circuit 17 into the water supply pump trip circuit 16, the hydraulic system that drives the steam control valves 7 and 7B, which could not be detected in the conventional example, Detects an abnormality in the water supply control device due to failure of the valve), and sends an MD-RFP activation signal or a TD-RFP
) outputs a rip signal.

The function of the trip determination circuit 17 will be explained below based on FIG.

The functions of the trip determination circuit 17 are roughly divided into two parts: one is to output the MD-RFP activation signal, and the other is to output the TD-RFP) lip signal.

First, the function of outputting the MD-RFP activation signal will be explained.

The deviation between the main steam flow rate signal 815 and the feed water R and amount multiplied signal I< is determined by the deviation determination unit 41. The abnormality determination unit 42 is.

If the deviation output from the deviation determination unit 41 exceeds the specified value for a certain period of time or more, and if an abnormality signal is output from the abnormality determination unit 42, the AND gate 43 outputs a signal “1”. do. In this case, MD
RFP activation signal, i.e. circuit breaker closing signal So and 812
is output to the corresponding MD-RFPQA and circuit breakers 31A and 31B of 9B. The water supply controller 15 outputs a reactor water level low signal 817 when the input reactor water level signal SIg becomes below a predetermined level. This predetermined level is set between level II + normal reactor water level, which will be described later. Instead of inputting the reactor water level low signal sty, the trip determination circuit 17 inputs the reactor water level signal St.
When a is input and the atomic f water level signal Sta becomes below a predetermined level, the reactor water level low signal 817 is sent to the AND gate 4.
It may also include a water level abnormality determination section that outputs the output to the water level abnormality determination section 3. The circuit breakers 31A and 31B receive circuit breaker close signals Sll and S1□
By inputting , the circuit enters the closed state and starts supplying drive current to the motors and IOB.

Therefore, MD-RFPQA and 9B are activated.

Next, the function of outputting the TD-FP trip signal in the trip determination circuit 17 will be explained.

The response of the turbine rotational speeds of TD-R, F'P4A and 4B can be sufficiently simulated by providing a simple delay in the input turbine rotational speed request signals SR and S2 in the delay circuit 18. Therefore, the deviation determination unit 19 determines the deviation between each turbine rotation speed output from the delay circuit 1B and the input rotation speed signals S5 and S6 for each TD-RFP. If the deviation output from the deviation judgment section 19 exceeds the specified value for a certain period of time or more, the abnormality determination section 20 outputs an abnormality signal that determines that the TD-RFP corresponding to the deviation is abnormal.

Furthermore, the valve opening degrees of the steam control valves 8A and 8B are as follows.

The response can be simulated by providing a delay to the turbine rotational speed request signals 81 and S2 in the delay circuit 21.

A deviation determining section 22 determines the respective deviations between each valve opening output from the delay circuit 21 and the input valve opening signals S7 and Sf for each steam control valve 11A and IIB. The abnormality determining unit 23 outputs an abnormality signal that determines that the TD-4FP corresponding to the deviation is abnormal when the deviation output from the deviation determining unit 22 exceeds the regulation for a certain period of time or more. The AND and OR gate 43 outputs a signal "1" indicating an abnormality when both the signals output from the abnormality determining sections 20 and 23 are abnormal signals or when only one of the output signals is an abnormal signal. Output. When the AND and OR gate 43 outputs the signal "1" and the AND gate 43 also outputs the signal "1", the AND gate 46 outputs the signal "1".

OR gate 24 is AND gate 46 or TD-RFP
rl when the output of the trip determination circuit 25 is "1"
Output J. When the AND gate 46 outputs "1", the water pump trip circuit 16 outputs "1".

The TD-RFP signal, that is, the steam stop valve closing signal Ss (or Sl.), is sent to the corresponding I''D-RF.
Output to steam stop valve 8N (still 8B) of P. The steam stop valve 8A (or 8B) receives the steam stop valve closing signal S9.
(or Sho) to stop supplying steam to turbine 5A (- or 5B). Therefore, TD-LE FP4A (or 4B>) is tripped.

The effects of the present embodiment shown above are as follows: T1)-RFP when two units are in operation at the rated output operation of the boiling water type atomic converter].
An example will be explained in which an abnormality occurs in the hydraulic system that operates the steam control valve 7A corresponding to one of the TD-RFPs (for example, four TD-RFPs).

If the steam control valve 7A that regulates the amount of steam supplied to the five turbines of TD-RFP4A is closed due to a failure in the hydraulic system, the steam flowing into the five turbines will be lost and the rotational speed of the five turbines will decrease. do.

Due to the decrease in the rotational speed of this turbine 5A, TD-RFP4A
The flow rate of water supply discharged from the reactor pressure vessel 1 decreases, and the total flow rate of water supply to the reactor pressure vessel 1 decreases. Therefore, as shown in FIG. 1, the reactor water level begins to drop due to a mismatch between the total steam flow rate and the total feed water flow rate.

However, in the embodiment, the steam stop valve 8A is closed by the function of the water pump trip circuit 1G as described above. ,
When the steam stop valve closing signal S9 output from the water supply pump trip circuit 16 is input, the steam stop valve 8A is set to G"t.
Since the hydraulic pressure applied to the hydraulic system operated by the steam stop valve 8A suddenly drops to Cσ, the steam stop valve 8A closes.

The hydraulic pressure of the hydraulic system of the steam stop valve 8A is detected by the pressure gauge 17 (not shown), and the regulator 8 (not shown) is activated when the output value of the pressure gauge falls below a predetermined value. Close the circuit breakers 31A and 31B of the two MD RFPs 9A and 9B.
B starts automatically, and as shown in FIG. 1, the total water supply flow rate decreases and increases.

Accordingly, the water level in the reactor stopped decreasing and began to rise.
・Return to normal reactor water level. Reactor scrams are avoided.

As mentioned above, not only when the steam regulating valve is closed due to a failure in the hydraulic system, but also when the steam regulating valve is opened due to galling of the valve body while the opening of the steam regulating valve is increasing or due to an abnormality in the hydraulic system. When the increase in temperature is stopped, the steam stop valve is also closed and TD-R and F'P are tripped. That is, the rotation speed of the turbine 5A (or 5B) is extremely low and the fgl difference from the turbine rotation speed request signal S+ (also hsz+) exceeds the specified value tL (i- for a certain period of time), so the steam stop valve is closed. .

In addition, one of the water supply control units of the embodiment] l is the following machine or 512) - or the steam stop valve closing signal (89 or 5
ha) is being output and the reactor water level is at level l.
(If it drops below l, the reactor recirculation pump 3
Be able to run back 3.

Level H1 is the correct level of water level in the secondary reactor and reactor? The level of the reactor water level that needs to be scrammed is set between 1t, which is a novelty. TD-)(, When the reactor water level falls below level H1 with the FP (or MD-RFP) tripped, it means that the standby MD-RFP has not been activated.

The functions of such a water supply control device will be specifically explained. It is assumed that eight steam stop valves are closed based on the steam stop valve closing signal S9 as described above. The water supply controller 15 outputs steam stop valve closing signals S9 and 81G and circuit breaker closing signals Stt.
and 812 can be input. At least one of these signals 89 to S12 (for example, signal 8s) t
-When done manually.

The water supply controller 15 uses a level determination unit (not shown) to determine whether the level of the input output signal (reactor water level signal) Sts from the water level gauge 12 has fallen below level H1.

When the output signal of the water level gauge 12 is lower than the level Hr, a run pack request signal 813 is output. The recirculation flow rate control device 1f34 receives the run pack request signal 81.
Enter 3 to run pack the recirculation pump 33. The rotational speed of the recirculation pump 33 is rapidly reduced by the run pack, and the flow rate of cooling water supplied to the reactor core 2 is rapidly reduced. As a result, the reactor power is reduced and the amount of steam generated l is reduced, so that a drop in the reactor water level is prevented.

In this practical example, TD-RFP or MD-F'P
Even if the reactor water level falls below level H in a tripped state, a reactor scram is prevented.

In this embodiment, a level determination section is provided in the water supply controller 15 and the runback request signal SI3 is output from the water supply controller 15, but a separate controller performs level determination and outputs the runpack request signal 81g. You may go.

In the conventional water supply control device, there are 7 steam control valves and 7 steam control valves.
Even if the hydraulic system for operating at least one of B fails and its steam control valve becomes, for example, fully closed, the hydraulic system for operating the steam stop valve will not drop below a predetermined value. The steam stop valve is closed in the conventional water pump trip circuit without the function of the trip judgment circuit 17, that is, TD-R,
Unable to trip FP.

In the embodiment described above, in addition to starting the MD RFP based on the abnormal state of the deviation between the main steam flow rate and the feed water flow rate, the TD-RFP is started based on the abnormal state of the turbine rotation speed and the valve opening of the steam control valve. However, it is also possible to trip the TD-R and FP based on the abnormal state of state 1 other than the rotation speed or valve opening degree described above.

For example, for each of the valve opening degree signals S7 and S8 of the steam control valves 7A and 7B, the variation width of the valve opening degree is determined, and if this variation width exceeds the specified value, each steam stop valve is closed. 1g issue S9. Output S1o. The subsequent operations are the same as the embodiment shown in FIG. The structure of this embodiment other than the above is the same as that of the embodiment shown in FIG. This embodiment also has a run pack function of the recirculation pump 33 like the embodiment shown in FIG. 1, and the same effects as the embodiment shown in FIG. 1 can be obtained.

Other embodiments of the present invention will be described. This example is.

In the trip determination circuit 17 shown in FIG. 2, a differential circuit for determining the rate of change of the steam control valve opening signals S7 and 8g and a differential circuit for determining the rate of change of the turbine rotational speed request signals S1 and S are provided, respectively. Depends.

The steam control valve opening degree change rate and the turbine speed request signal change rate are input to the deviation determination section 22 to determine the deviation, and if this deviation exceeds the specified value for a certain period of time or more, the deviation is Corresponding TD-RFPt- is one of the conditions to be considered abnormal. The subsequent operations are the same as in the embodiment shown in FIG.

The structure of this embodiment other than the above is the same as that of the embodiment shown in FIG. This embodiment also has a run pack function of the recirculation pump 33 like the embodiment shown in FIG. 1, and the same effects as the embodiment shown in FIG. 1 can be obtained.

Each of the embodiments described above is applied to a boiling water type atomic couplant. However, the invention is also applicable to other steam generation plants, such as pressurized water nuclear couplants and thermal power plants. That is, in pressurized water atomic couplants and thermal power plants.

In the embodiment shown in FIG. 1, only the reactor pressure vessel 1 is replaced by a steam generator and a boiler, and the water supply system is the same. Therefore, in these steam generation plants, the signal output from the water level gauge 12 in FIG.
However, in the IJO pressure water type atomic reactor, it is used as a control device for control drive equipment and a poison concentration control device, and also as a governor control device in a thermal power plant. Even when the present invention is applied to a steam generation plant, the same effects as the embodiment shown in FIG. 1 can be obtained.

〔Effect of the invention〕

According to the present invention, when an abnormality occurs in the flow rate of steam generated from the steam generator and the flow rate of water supplied to the steam generator while the turbine-driven water supply pump is being driven, the motor-driven water supply on standby The pump can be started quickly.

Also, while the turbine-driven water supply pump is in operation.

Even if an abnormal decrease in the opening of the steam regulator valve occurs, the water supply unit corresponding to the steam regulator valve can be tripped.
Other water supply pumps on standby can be started promptly. Therefore, even if an abnormal decrease in the opening of the drain control valve occurs while the water supply pump is being driven, it is possible to avoid stopping the operation of the steam generator due to a significant drop in the water level within the steam generator. This results in
The operation rate of the steam generation plant will improve.

In addition, the reliability of the IJ knob signal (water supply pump) is improved by outputting it when multiple conditions are met, making it possible to avoid erroneous trips due to erroneous signals.

[Brief explanation of drawings]

Fig. 1 is a direct line diagram of one embodiment of the present invention, Fig. 2 is an explanatory diagram showing detailed interlock of the water supply pump trip circuit in Fig. 1, and Fig. WJ3 is the TD-RFP lip judgment circuit in Fig. 2. Fig. 1 is a diagram showing plant behavior when an abnormality occurs in the turbine and drive water pump in Fig. 1, and Fig. 5 shows a diagram of the plant behavior when an abnormality occurs in the turbine-driven water pump using the conventional technology. It is a plant behavior diagram.

Claims (1)

[Claims] 1. A steam generator, a condenser, a steam pipe for supplying steam generated from the steam generator, and a water supply pipe for guiding water supply from the condenser to the steam generator. , a water supply control device for a steam generation plant having a turbine-driven water supply pump provided in the water supply pipe; and a motor-driven water supply pump provided in the water supply pipe in parallel with the turbine-driven water supply pump; means for detecting a flow rate, means for detecting a steam flow rate in the steam piping, means for detecting a water level inside the steam generator, a feed water flow rate signal output from the feed water flow rate detection means and the main steam flow rate detection means. control means for starting the motor-driven water supply pump when there is an abnormality in the deviation from the main steam flow rate signal output from the main steam flow rate signal and when there is an abnormality in the water level signal output from the water level detection means. Featuring water supply control equipment for steam generation plants. 2. Means for detecting the rotation speed of the turbine for driving the turbine-driven water supply pump, and means for detecting the opening degree of the steam control valve of the turbine for driving the turbine-driven water supply pump, wherein the rotation speed is output from the rotation speed detection means. rotation speed signal and
It is characterized by comprising a valve opening degree signal outputted from the valve opening degree detection means and a control means for tripping the turbine-driven water supply pump when there is a deviation abnormality as set forth in claim 1. Water supply control equipment for steam generation plants. 3. The water supply control device for a steam plant according to claim 1, wherein the abnormality in the deviation between the feed water flow rate and the main steam flow rate occurs when the deviation exceeds a specified deviation value for a predetermined period of time. 4. An abnormality in the rotational speed signal is a case where the deviation between the rotational speed signal output from the rotational speed detection means and the speed request signal of the driving turbine exceeds a specified value for a predetermined period of time; Furthermore, the abnormality in the valve opening signal occurs when the deviation between the valve opening signal output from the valve opening detection means and the speed request signal of the driving turbine exceeds a specified value for a predetermined period of time. A water supply control device for a steam generation plant according to claim 2. 5. The abnormality in the valve opening is caused by a predetermined deviation between the variation width or rate of change of the valve opening signal output from the valve opening detection means and the variation width or rate of change of the speed request signal of the driving turbine. The water supply control device for a steam generation plant according to claim 2, which is a case where the water exceeds the specified value for a period of time.