JPH0665924B2 - Water supply controller for steam generating plant - Google Patents

Description

TECHNICAL FIELD The present invention relates to a water supply control device for a steam generation plant, and more particularly to a water supply control device for a steam generation plant suitable for application to a boiling water nuclear power plant.

[Prior Art] A conventional feed water control apparatus for a boiling water nuclear power plant is shown in Fig. 1 of page 16 of JP-A-57-197499. The water supply control device that supplies water to the reactor pressure vessel of a boiling water nuclear power plant, which is a type of steam generator, is driven by a steam turbine that uses the steam generated in the reactor pressure vessel.
% Capacity turbine driven water pump (hereafter TD-RFP
Abbreviated) and two motor-driven water supply pumps (hereinafter abbreviated as MD-RFP) with a capacity of 25% driven by an electric motor. M
The D-RFP is used for starting and shutting down the reactor in which steam generated in the reactor pressure vessel cannot be used, or as a backup when the TD-RFP is stopped. Therefore, during normal operation, two TD-RFP units will be operated.

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

The feed water flow rate discharged from the TD-RFP is adjusted by adjusting the steam control valve opening that controls the amount of steam supplied to the drive turbine of the TD-RFP according to the drive turbine speed request signal output from the water supply controller. By doing.

On the other hand, MD-RFP is driven by an electric motor that rotates at a constant speed.
The water supply flow rate is adjusted by controlling the opening of the water supply adjustment valve provided on the discharge side of the D-RFP according to the valve opening request signals 10 and 11 output from the water supply control device.

When an abnormality is detected and it is necessary to trip the water supply pump, the water supply pump trip device trips the water supply 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 (which is a steam flow rate control valve). In addition, MD-RFP is tripped by opening the breaker of the drive motor by the water supply pump trip device. As a factor of the water supply pump trip,
Abnormal signals on the plant side such as stop of condensate pump, low suction pressure of TD-RFP, high reactor water level, etc. When either of these signals is output, the control oil of the steam stop valve is drained and the steam stop valve is closed rapidly. With the closing of this valve, the steam supply to the drive turbine is shut off and the TD-RFP is stopped.

Next, the behavior of the boiling water nuclear plant when the feed pump trips for some reason will be described.

(1) When one of the TD-RFPs trips during operation When one of the TD-RFPs trips, the control hydraulic pressure drop of the turbine steam stop valve for pump drive is detected and the trip of the TD-RFP is judged to supply water. 2 MD-RFPs promptly by the control device
To start automatically. If the MD-RFP does not start automatically, the speed of the recirculation pump that supplies cooling water to the reactor core is suddenly reduced when the reactor water level drops to a certain set value (hereinafter, recirculation pump runback). It reduces the reactor power and suppresses steam generation.
As a result, it is possible to avoid the scram of the reactor due to the decrease in the reactor water level.

(2) When the pump trips while one TD-RFP is operating Two MD-RFPs are automatically started as in (1) to prevent the reactor water level from decreasing.

(3) When the pump trips while one MD-RFP is operating The stopped MD-RFP automatically starts and compensates for the water supply of the tripped MD-RFP to prevent the reactor water level from decreasing.

[Problems to be Solved by the Invention] As a result of a detailed study by the inventors of the function of a conventional water supply control device, a hydraulic system (for example, a servo valve) that inputs an output signal of a turbine control device to control a steam control valve It has been found that the steam control valve (steam flow control valve) may be closed irrespective of the control signal output from the turbine control device when an abnormality occurs in the servo motor). In such a case, the supply steam to the drive steam turbine is lost, and the turbine speed is rapidly reduced.

However, since the trip signal of the feed pump is not generated (the steam stop valve is not closed), MD-RFP is not automatically activated. As a result, as shown in FIG. 5, the feed water pump flow rate decreases and the total feed water flow rate also decreases, leading to the reactor scrum due to the low reactor water level. The characteristic of Fig. 5 is that one TD out of two TD-RFPs in operation.
-When the steam control valve for adjusting the steam supply amount of the RFP is closed as described above.

In addition, even when one MD-RFP is operating, the water supply adjustment valve (water supply flow rate control valve) is closed due to a failure of the electropneumatic converter that converts the control signal output from the water supply control device into air pressure,
Drive the MD-RFP drive circuit breaker without opening the MD-RFP
It was also found from the above-mentioned study that the discharge flow rate of P may be lost. In this case also, since the MD-RFP trip signal is not generated, the other MD-RFP does not start automatically. As with the failure of the hydraulic system in TD-RFP described above, the atom due to the low reactor water level is used. To the furnace scrum. In addition,
The steam control valve and the water supply control valve are flow rate control valves.

It is an object of the present invention to provide a water supply control device for a steam generating plant, which can prevent the steam generator from stopping due to the closing of a flow rate control valve while the water supply pump is being driven.

[Means for Solving the Problem] With respect to the TD-RFP, the above object is to provide a rotation speed detecting means for detecting the rotation speed of the turbine-driven feed water pump, and a water supply control for outputting a rotation speed control signal of the turbine-driven water supply pump. means,
And a control means for tripping the turbine driven water feed pump when the deviation between the rotation speed control signal and the rotation speed signal output from the rotation speed detection means exceeds a set value. Detecting the rotational speed of the driving turbine of the TD-RFP is equivalent to detecting the rotational speed of the pump connected to the driving turbine.

Further, for MD-RFP, from the opening detection means that detects the opening of the flow rate control valve, the water supply control means that outputs the opening control signal of the flow rate control valve, and the opening control signal and the opening detection means. This is achieved by providing control means for tripping the motor-driven water supply pump when the deviation from the output opening signal exceeds a set value.

[Operation] By detecting an abnormality in the rotational speed of the TD-RFP drive turbine, that is, when the deviation between the rotational speed control signal and the rotational speed signal output from the rotational speed detection means exceeds a set value, TD-RFP is tripped, and this trip causes MD-R
Since the FP is activated, it is possible to suppress the decrease in the water level in the steam generator and prevent the steam generator from shutting down. In addition, MD-RF
For P, by detecting an abnormality in the opening of the feedwater flow rate control valve, that is, when the deviation between the opening control signal and the opening signal output from the opening detection means exceeds a set value,
The MD-RFP is tripped, and the other MD-RFP in the standby state is activated by this trip, so that the water level in the steam generator can be suppressed and operation stop of the steam generator can be prevented.

[Embodiment] A feed water control apparatus for a steam generating plant, which is a preferred embodiment of the present invention applied to a boiling water nuclear power plant, will be described below with reference to Figs. 1 and 2. The reactor pressure vessel of a boiling water nuclear power plant is a steam generator.

During normal operation of the boiling water nuclear power plant, the cooling water (feed water) heated in the core 2 in the reactor pressure vessel (steam generator) 1 becomes steam. This steam is discharged from the reactor pressure vessel 1 and sent to the turbine (not shown) through the main steam pipe 2. The steam exhausted from the turbine is condensed into water by a condenser (not shown). Condensed water discharged from the condenser, that is, feed water serving as cooling water for the reactor, is supplied to the feed water pipe 3 by a condensate demineralizer (not shown), a condensate pump (not shown), and low-pressure feed water heating. To a container (not shown). Furthermore, the water supply is divided into branch pipes 3A and 3B of the water supply pipe.
It is pressurized by the two TD-RFPs 4A and 4B provided in the reactor, heated by the high-pressure feed water heater, and supplied into the reactor pressure vessel 1. Although not shown, the extraction steam of the main steam pipe 2 is supplied to the low-pressure and high-pressure feed water heaters as a heating source for the feed water. The extracted steam is condensed in the feed water heater and introduced as a drain to the condenser.

The TD-RFPs 4A and 4B are connected to the extraction pipe 6 from the turbine (not shown).
It is driven by supplying the steam extracted in A and 6B to turbines 5A and 5B, respectively. Although not shown, these injected steam is exhausted to a low-pressure feed water heater.
The rotation speed control of the TD-RFPs 4A and 4B is performed by adjusting the flow rate of the extraction steam supplied to the turbines 5A and 5B by opening and closing the steam control valves 7A and 7B provided in the extraction pipes 6A and 6B.
MD-RFPs 9A and 9B provided in the branch pipes 3C and 3D of the water supply pipe 3 are in a standby state for backup of the TD-RFPs 5A and 5B during normal operation of the reactor. MD-RFP9A is driven when the reactor starts up and shuts down. MD-RFP9B
Is also used as a backup for MD-RFP9A. MD
-The flow rate control of the feed water supplied by RFP 9A and 9B is performed by the feed water regulating valve (flow regulating valve) 11A provided in the branch pipes 3C and 3D.
And 11B. Turbine steam control valves 7A and 7B
And, the control of the feed water flow rate by the feed water regulating valves 11A and 11B is performed by a water level gauge 12 for measuring the water level in the reactor pressure vessel 1, a feed water flow meter 13 provided in the feed water pipe 3, and a main steam provided in the main steam pipe 2. It is performed by the water supply controller 15 which inputs the measurement value of the flow meter 14. The water supply controller 15 is the M-RFP controller 36 and the function generator 4 shown in FIG. 1 of JP-A-57-197499, page 16.
9 and turbine speed controller 48. In the above publication, the motor-driven water supply pump is referred to as M-RFP. The feed pump trip circuit 16 has a trip determination circuit 17, a TD-RFP trip determination circuit 25, and an MD-RFP trip determination circuit 28. Water pump trip circuit 16
The details of the logic are shown in FIG. Details of the logic of the TD-RFP trip determination circuit 25 are shown in FIG. MD-RFP
The logic of trip decision circuit 28 is TD-RF shown in FIG.
In the logic of the P trip determination circuit 25, "TD-RFP" is changed to "MD-
Equivalent to replacing the RFP.

2 and 3, 24, 27 and 26 are OR gates, and 35 is an AND gate.

The water supply control device of the present embodiment has a water level gauge 12, a water supply flow meter 13,
It has a main steam flow meter 14, a water supply controller 15, a water supply pump trip circuit 16, tachometers 29A and 29B, and opening detectors 30A and 30B.

Tachometers 29A and 29B are attached to the rotating shafts of turbines 5A and 5B. These tachometers may be attached to the rotary shafts of the TD-RFPs 4A and 4B connected to the rotary shafts of the turbines 5A and 5B. The opening detectors 30A and 30B are the water supply adjusting valves 11A and 11B.
It is provided in.

At startup of a boiling water nuclear plant, the reactor pressure vessel 1
The control rod 32 inserted into the reactor core 2 therein is pulled out, and the temperature raising and pressurizing operations in the reactor pressure vessel 1 are performed. The supply of water supply into the reactor pressure vessel 1 is performed through the water supply pipe 3. MD-RFP2 unit operation, TD-
The operation of the water supply pump is switched to the operation of one RFP and the operation of two TD-RFPs. During normal operation of the reactor, the TD-RFP4A
And 4B are in operation. The water supply controller 15 controls the water supply flow rate in MD-RFP and TD-RFP. That is, the feed water controller 15 inputs three signals of the reactor water level, the feed water flow rate and the steam flow rate detected by the water level meter 12, the feed water flow meter 13 and the main steam flow meter 14, respectively, and these three signals are input. The turbine rotation speed request signals S ₁ and S ₂ of the TD-RFPs 4A and 4B created by the P and I operations of The steam control valves 7A and 7B have their turbine speed request signals S ₁ and
Valve opening in response to the request signals S ₁ and S ₂ by entering the S ₂ is adjusted. Therefore, the feed water flow rate discharged from the TD-RFPs 4A and 4B is adjusted. The water supply controller 15 is MD-
When the RFP 9A or 9B is driven, the valve opening request signals S ₃ and S ₄ of the feedwater adjusting valves 11A and 11B obtained by the PI calculation of the input reactor water level, feedwater flow rate and steam flow rate are output. The water supply adjusting valves 11A and 11B are the input valve opening request signals.
Adjust the valve opening according to S ₃ and S ₄ . Therefore, MD-RF
The flow rate of water supplied from P9A and 9B is adjusted.
By thus controlling the feed water flow rate by the feed water controller 15, the reactor water level is controlled to be constant.

In this embodiment, the turbine speed signals S ₅ and S ₆ output from the tachometers 29A and 29B, the turbine speed request signal S ₁ and
S ₂ , valve opening signal S ₇ output from opening detectors 30A and 30B
And S _8, by providing capture the valve opening request signal S ₃ and S ₄ to the water supply pump trip circuit 16, the trip judgment circuit 17 to the feed water pump trip circuit 16, steam control valve 7A and could not be detected in the prior art It detects the abnormality of the water supply control device due to the failure of the hydraulic system (servo valve) that drives 7B, and outputs the water supply pump trip signal when there is an abnormality.

The function of the trip determination circuit 17 will be described below with reference to FIG.

The response of the turbine speeds of the TD-RFPs 4A and 4B can be sufficiently simulated by allowing the input turbine speed request signals S ₁ and S ₂ to have a simple delay in the delay circuit 18. Therefore, the deviation between the turbine rotational speed output from the delay circuit 18 and the input rotational speed signals S ₅ and S ₆ is calculated by the deviation determining unit 19 for each TD-RFP. The abnormality determination unit 20 includes the deviation determination unit 19
If the deviation output from the TD-RFP exceeds the specified value for a certain time or longer, the TD-RFP corresponding to the deviation
The regarded as abnormal TD-RFP trip signal, i.e. steam stop valve closing signal S ₉ (or S ₁₀₎ steam stop valve 8A for outputting a steam stop valve 8A of the corresponding TD-RFP (or 8B) (or 8B) Is closed by inputting the steam stop valve closing signal S ₉ (or S ₁₀ ) to stop the supply of steam to the turbine 5A (or 5B). This causes TD-RFP4A (or 4B) to trip.

Further, valve opening of the water supply control valve 11A and 11B can simulate response by providing a delay in valve opening request signal S ₃ and S ₄ to the delay circuit 21 input. The deviation determination unit 22 obtains the deviation between each valve opening output from the delay circuit 21 and the input valve opening signals S ₇ and S ₈ for each water supply adjusting valve 11A and 11B. Abnormality determination unit 23, MD-RF upstream of the water supply regulating valve corresponding to the deviation when the deviation output from the deviation determination unit 22 exceeds the specified for a certain time or more
P is regarded as abnormal and the MD-RFP trip signal, that is, the circuit breaker open signal S ₁₁ (or S ₁₂ ) is output to the circuit breaker 31A (or 31B) of the corresponding MS-RFP 9A (or 9B). Circuit breaker 31
A (or 31B) is opened by inputting the circuit breaker open signal S ₁₁ (or S ₁₂ ) and the motor 10A (or 1
Supply of drive current to 0B) is stopped. Therefore, MD-RF
P9A (or 9B) is tripped.

The operation of the present embodiment shown above is performed by operating the steam control valve 7A corresponding to one TD-RFP (for example, TD-RFP4A) that is operating two at the rated output operation of the boiling water nuclear power plant. A case where a system abnormality occurs will be described as an example.

When the steam control valve 7A for adjusting the amount of steam to be supplied to the turbine 5A of the TD-RFP 4A is closed due to a failure of the hydraulic system or the like, the steam flowing into the turbine 5A is lost and the rotation speed of the turbine 5A is reduced. TD-
The feed water flow rate discharged from RFP4A decreases, and the total feed water flow rate to the reactor pressure vessel 1 decreases. Therefore, as shown in Fig. 4, the reactor water level begins to drop due to the mismatch between the total steam flow rate and the total feed water flow rate.

However, in the embodiment, as described above, the steam stop valve 8A is closed by the function of the feed pump trip circuit 16. Steam stop valve closing signal output from feed pump trip circuit 16
When S ₉ is input, the hydraulic pressure applied to the hydraulic system that operates the vapor stop valve 8A to open the vapor stop valve 8A sharply drops, so the vapor stop valve 8A closes.

When the hydraulic pressure of the hydraulic system of the steam stop valve 8A is detected by a pressure gauge (not shown), and the controller (not shown) reduces the output value of the pressure gauge below a predetermined value, the two MD-standby units
Close circuit breakers 31A and 31B of RFP 9A and 9B. This makes M
D-RFP9A and 9B are automatically started, and the total feedwater flow rate that has decreased as shown in Fig. 4 increases. In accordance with this, the reactor water level will begin to rise after the decrease has settled, and will return to the normal reactor water level. Reactor scrum is avoided.

As described above, not only when the steam control valve is closed due to a failure of the hydraulic system, but also when the steam control valve opens while the opening of the steam control valve is increasing or due to an abnormality in the hydraulic system. The steam stop valve is also closed and the TD-RFP is tripped when the increase is stopped. That is, since the rotation speed of the turbine 5A (or 5B) is extremely low and the deviation from the turbine rotation speed request signal S ₁ (or S ₂ ) exceeds the specified value for a certain period of time or longer, the steam stop valve is closed.

Furthermore, the water supply control device of this embodiment has the following functions. That is, when the steam stop valve closing signal or the circuit breaker opening signal is output and the reactor water level falls below the level H _{1, the} recirculation pump 33 of the reactor can be run back. The level H ₁ is a level set between the normal reactor water level and the reactor water level at which the reactor needs to be scrammed. TD-RF
If the reactor water level falls below level H _{1 while} P (or MD-RFP) is tripped, it means that the standby MD-RFP was not activated.

The function of such a water supply control device will be specifically described. As described above, it is assumed that the steam stop valve 8A is closed based on the steam stop valve closing signal S ₉ . The water supply controller 15 can input the steam stop valve closing signals S ₉ and S ₁₀ and the circuit breaker opening signals S ₁₁ and S ₁₂ . When at least one of these signals S _{9 to} S ₁₂ is input (for example, signal S ₉ ), the water supply controller
15 is the output signal of the input water level gauge 12 (reactor water level signal)
The level determination unit (not shown) determines whether or not the level is lower than the level H ₁ . When the output signal of the water level gauge 12 is lower than the level H ₁ , the runback request signal S ₁₃ is output. The recirculation flow controller 34 causes the recirculation pump to run back by inputting the runback request signal S ₁₃ . The rotation speed of the recirculation pump 33 is drastically reduced by the runback, and the flow rate of the cooling water supplied to the core 2 is drastically reduced. As a result, the reactor output decreases and the amount of steam generated decreases, so that the reactor water level is prevented from decreasing. In the practical example of the present embodiment, even if the reactor water level falls below the level H while the TD-RFP or MD-RFP is tripped, the reactor scram is prevented from being reached.

This embodiment, the water supply controller 15 provided with a level determining unit to the water supply controller 15 has outputs the run-back request signal S _13, by a separate controller of the level decision and the run-back request signal S ₁₃ You may output.

In the conventional water supply control device, even if the hydraulic system for operating at least one of the steam control valves 7A and 7B fails and the steam control valve is fully closed, for example, the hydraulic pressure for operating the steam stop valve Since the system does not drop below the predetermined value, the steam stop valve cannot be closed, that is, TD-RFP cannot be tripped by the conventional feed pump trip circuit without the function of the trip determination circuit 17.

In the above-described embodiment, the TD-RFP or MD-RFP is tripped based on the abnormal state of the rotational speed of the turbine or the valve opening degree of the feed water adjustment valve, but the state other than the aforementioned rotational speed or valve opening degree is used. It is also possible to trip the TD-RFP based on an abnormal volume condition.

For example, the steam control valves 7A and 7B are provided with opening detectors in the same manner as the water supply adjusting valves 11A and 11B, and the output signals (valve opening signals) of these opening detectors are used instead of the rotation speed to determine the trip determination circuit 17A.
Of the delay circuit 18 and the valve opening signal to obtain the deviation, and when the deviation exceeds the specified value for a certain period of time or more, the steam stop valve closing signal S
Outputs ₉ (or S ₁₀ ). The subsequent operation is the same as that of the embodiment shown in FIG. The configuration of the parts other than the above in this embodiment is
This is the same as the embodiment shown in FIG. This embodiment also has the run-back function of the recirculation pump 33 as in the embodiment of FIG. 1, and the same effect as that of the embodiment of FIG. 1 can be obtained.

Another embodiment of the present invention will be described. In this embodiment, the extraction tubes 6A on the downstream side of the steam control valves 7A or 7B shown in FIG.
Alternatively, a pressure gauge is provided in the portion 6B, particularly in the portion of the extraction pipe 6A between the steam control valve 7A and the turbine 5A (the same portion for the extraction pipe 6B). The extraction steam pressure signal that is the output of this pressure gauge and the reactor water level signal that is the output of the water gauge 12 are the trip determination circuit 17 of the feed pump trip circuit 16.
Entered in. Trip determination circuit used in this embodiment
17 is different from that shown in FIG. 2 in that the delay circuit 18 and the deviation judging section 19 are not provided and the judging function of the abnormality judging section 20 is different, but the other parts are the same. The extracted steam pressure signal and the reactor water level signal are input to the abnormality determination unit 20. The abnormality determination unit 20 determines that an abnormality has occurred in the extraction steam pressure signal when the level of the reactor water level signal is lower than the level H _{2 and the} extraction steam pressure signal is lower than the predetermined level. Then, the steam stop valve closing signals S ₉ and S ₁₀ are output. The subsequent operation is the same as that of the embodiment shown in FIG. The level H ₂ is set near the level H ₁ between the normal reactor water level level and the level H ₁ . The other structure of this embodiment is the same as that of the embodiment of FIG. 1, and the effect of this embodiment is the same as that of the embodiment of FIG.

A flow meter may be attached to the extraction pipes 6A and 6B at the same position as the pressure gauge, instead of the pressure gauge that outputs the extraction steam pressure signal. These flow meters detect the extracted steam flow rate and output an extracted steam flow rate signal. In this embodiment, the extracted steam flow rate signal is input to the abnormality determination unit 20 instead of the extracted steam pressure signal. The abnormality determination unit 20 determines that the extraction steam flow rate signal is abnormal when the reactor water level signal is lower than the level H ₂ and the extraction steam flow rate signal is lower than a predetermined level.
The steam stop valve closing signals S ₉ and S ₁₀ are output. The subsequent operation is the same as that of the embodiment using the extracted vapor pressure signal. The effects and other configurations of this embodiment are the same as those of the embodiment using the extracted steam pressure signal.

Further, in the embodiment of the extracted steam pressure signal, there is no functional change even if the hydraulic signal of each hydraulic system for opening / closing the steam control valves 7A and 7B is used instead of the extracted steam pressure signal.
These hydraulic signals can be detected by providing a pressure gauge in each hydraulic system. The abnormality determining unit 20 outputs the steam stop valve closing signals S ₉ and S ₁₀ when the hydraulic signal along with the reactor water level signal becomes lower than a predetermined level.

The abnormality determination units 20 and 23 of each of the embodiments described above are portions that determine whether or not there is an abnormal decrease in the opening of the flow rate control valve (for example, the steam control valves 7A and 7B and the water supply control valves 11A and 11B). The water supply pump trip circuit 15 of each embodiment having such an abnormality determination unit is a control unit that trips the TD-RFP or MD-RFP when an abnormal decrease in the flow control valve opening degree occurs.

The embodiments described above are applied to the boiling water nuclear power plant. However, the invention is also applicable to other steam generating plants, such as pressurized water nuclear plants and thermal power plants. That is, in the pressurized water nuclear power plant and the thermal power plant, the reactor pressure vessel 1 in the embodiment of FIG. 1 only replaces the steam generator and the boiler, and the water supply system is the same. Therefore, in these steam generating plants, the signal output from the water level gauge 12 in FIG. 1 is used as the steam generator water level signal and the boiler water level signal, and the recirculation flow rate control device 34 controls the pressurized water nuclear power plant. It will also be a governor controller in a thermal power plant as well as a rod drive controller and poison concentration controller. Even when the present invention is applied to a steam generating plant, the same effect as that of the embodiment shown in FIG. 1 can be obtained.

[Effect of the Invention] According to the present invention, even if an abnormal phenomenon of the flow control valve opening occurs during the driving of the water supply pump, the water supply pump corresponding to the flow control valve can be tripped and is in the standby state. The other water pumps can be quickly started. Therefore, even if an abnormal phenomenon of the flow control valve opening occurs during the driving of the water supply pump, it is possible to avoid the stoppage of the operation of the steam generator due to a significant decrease in the water level in the steam generator. This improves the operating rate of the steam generation plant.

[Brief description of drawings]

FIG. 1 is a schematic diagram of an embodiment of the present invention, FIG. 2 is an explanatory diagram showing a detailed interlock of the feed water pump trip circuit of FIG. 1, and FIG. 3 is a TD-RFP trip determination circuit of FIG. 4 is an explanatory view showing an interlock of Fig. 4, Fig. 4 is a plant behavior diagram when an abnormality occurs in the turbine driven feed water pump in Fig. 1, and Fig. 5 is a plant when an abnormality occurs in the turbine driven feed water pump in the conventional technique. FIG. 1 ... Reactor pressure vessel, 2 ... Water supply piping, 4A, 4B ... Turbine driven water supply pump, 5A, 5B ... Turbine, 6A, 6B ...
… Bleed pipe, 7A, 7B …… Steam control valve, 8A, 8B …… Steam stop valve, 9A, 9B …… Motor driven water pump, 11A, 11B …… Water control valve, 12 …… Water level gauge, 13 …… Water supply flow meter, 14 ... Main steam flow meter, 15 ... Water supply controller, 16 ... Water supply pump circuit, 17 ... Trip determination circuit, 19, 22 ... Deviation determination unit,
20, 23 …… Abnormality judgment part, 29A, 29B …… Tachometer, 30A, 30B
…… Opening detector, 31A, 31B …… Breaker.

Claims (2)

[Claims] 1. A steam generator, a water supply pipe for introducing water to the steam generator, a turbine driven water supply pump provided in the water supply pipe, and a motor provided in the water supply pipe in parallel with the turbine driven water supply pump. In a water supply control device of a steam generation plant having a drive water supply pump, a rotation speed detection means for detecting the rotation speed of the turbine drive water supply pump, and a water supply control means for outputting a rotation speed control signal of the turbine drive water supply pump, Steam generation, comprising: a control means for tripping the turbine-driven feed water pump when a deviation between the rotation speed control signal and the rotation speed signal output from the rotation speed detection means exceeds a set value. Water supply control device for plant. 2. A steam generator, a water supply pipe for introducing water to the steam generator, a turbine driven water supply pump provided in the water supply pipe, and a motor provided in the water supply pipe in parallel with the turbine driven water supply pump. A water supply control device for a steam generating plant, comprising: a drive water supply pump; and a flow rate control valve that is connected to a discharge side of the motor drive water supply pump and is provided with the water supply pipe in parallel with the turbine drive water supply pump. Opening detection means for detecting the opening of the flow control valve, water supply control means for outputting the opening control signal of the flow control valve, deviation between the opening control signal and the opening signal output from the opening detection means And a control means for tripping the motor-driven feed water pump when the value exceeds a set value.