JP2004240905A - Operation support method and device of reactor for nuclear power generation - Google Patents

Abstract

<P>PROBLEM TO BE SOLVED: To provide an operation support method and device of a reactor for nuclear power generation for automatically determining abnormality of equipment related to nuclear power generation, automatically controlling the output, and further automatically establishing a contact with a relevant site. <P>SOLUTION: A control auxiliary device 11 of this invention is connected to a control rod operation handle 14 and reactor manual stop button 15 of a plant total control device 3. The measured volumes during operation from a main measuring instrument 8 and another measuring instrument 9 are automatically compared and determined with a preliminarily acquired and set range value by the software built in a computer 20, whereby abnormality is determined to control the output of the reactor, and the contact with the telephone or FAX of the relevant site is automatically established. <P>COPYRIGHT: (C)2004,JPO&NCIPI

Description

[0001]
TECHNICAL FIELD OF THE INVENTION
The present invention is a method and an apparatus for supporting operation of a nuclear reactor in nuclear power generation.
[0002]
[Prior art]
A plant monitoring and control device that monitors the reactor operation status and controls the output, and scrams when an accident occurs due to loss of primary coolant due to a major breakage of the primary piping or a decrease in flow rate due to stoppage of the primary coolant pump. The block diagram involved is shown in FIG. Arrows in the figure indicate directions in which information is transmitted. The state quantity from the main measuring device (8), which measures the water level of the reactor in the machine room (2) of the reactor, etc., is led to the plant general control device (3) in the central operating room (1) and is constantly monitored When a certain set value is exceeded, a control rod automatic insertion signal is transmitted to a control machine (7) such as a scrum, and a reactor called a scram is automatically stopped without human intervention. There is no human personal judgment, such as speculation. There is no intention or speculation about the site personnel of the organization that owns the power plant, the power plant manager, the manager, or the officials of the national or local government that oversees the power plant. The plant integrated control device (3) related to the automatic stop is a large-scale and has been almost completed by improvement based on past results. Significant alterations compromise the safety of the reactor because new problems may arise.
On the other hand, with regard to various abnormal events such as an increase in the shaft vibration of the cooling water circulation pump motor that does not result in automatic shutdown, the reactor is not automatically stopped because a large accident does not occur immediately. For an abnormal event that does not become a major accident in an emergency, but may cause a major accident if left unchecked, the measurement quantity from other measuring instruments (9) that measures the motor shaft vibration etc. An alarm signal is issued while being monitored by the recording device (19). On-site personnel such as operators and maintenance personnel judged and operated the control rod operation handle group (4) and pressed the reactor manual stop button (5) to control the reactor output. A telephone (6) is provided in the central operation room (1) for communication with the outside.
In general, shutting down equipment lowers the operating rate and raises costs. Shutting down nuclear power also lowers the operating rate and increases power generation costs. The larger the equipment, the higher the price. If the judgment is stopped by mistake, it becomes a liability issue. On the other hand, there is a possibility that a large accident may occur because the judgment is not stopped by mistake. In this way, personal speculation comes about the reactor shutdown time. In addition, if there is confusion, if you forget to contact the person you should contact, it may become a problem at a later date.
[0003]
[Problems to be solved by the invention]
SUMMARY OF THE INVENTION It is an object of the present invention to determine that an abnormal event has occurred, automatically determine a measure from a reactor power reduction to a manual reactor shutdown each time, and appropriately control the reactor power. It is another object of the present invention to automatically contact the outside appropriately according to the situation.
[0004]
[Means for Solving the Problems]
FIG. 2 is a block diagram relating to the plant operation support device of the present invention. Arrows in the figure indicate directions in which information is transmitted. By installing the control auxiliary device (11) of the present invention to the control rod operation handle group (14) and the reactor manual stop button (15) of the nuclear power plant integrated control device (3), it is installed on the observation target equipment. An object of the present invention is to determine the occurrence of an abnormal situation based on the measured amounts from the main detector (8) and the other detectors (9) and to control the reactor power while sequentially confirming the result of the determination each time. Furthermore, the purpose is to contact the power supply control center FAX (16), related local governments, the regulatory agency FAX (12), and the mobile phone (13) responsible for cancellation according to the situation.
FIG. 3 is a schematic view of the control auxiliary device (11) of the present invention. The arrows in the figure indicate the direction in which the signal is transmitted. A computer (20) surrounded by a two-dot chain line constantly inputs measurement amounts from the main measurement device (8) and other measurement devices (9) via a measurement amount input device (26), and performs calculation and signal transmission / reception control. If it is determined to be abnormal by calculation and monitoring by software incorporated in the unit (21), an image, a sound, a print display (22), a lamp switch operation unit (23) and an external related local government, Controlling the transmission to the regulatory agency FAX (12), the cell phone responsible for release (13), and the power supply command center FAX (16) to issue a warning, the control rod operation handle (14) of the plant integrated control device (3). ) And the reactor manual stop button (15) to automatically control the reactor power. If it is determined by the detailed examination of the engineer that there is no problem in the normal operation continuation, the alarm can be canceled by inputting the cancellation password from the person in charge of cancellation by the manual key (29). If the measured amount is normal, the lamp switch operating device (23) notifies that the target device is normal by blinking the green lamp (24), and if abnormal, blinks the red lamp (25).
[0005]
BEST MODE FOR CARRYING OUT THE INVENTION
The computer (20) constantly inputs a measured amount that does not reach the scrum from the main measuring device (8) and other measuring devices (9) installed in the monitored device, and if there is no abnormality in the monitored device, the green lamp (24) ) Flashes.
When the computer (20) determines that the monitored device is abnormal from the measured amount, the green lamp goes out and the red lamp (25) flashes. If the abnormality is completed in a short time and it is determined that it is accidental, the red lamp stops blinking and the green lamp blinks again.
When the abnormality progresses, the control rod operation handle group is automatically sent to the image, voice, print display (22), the release responsible mobile phone (13), and the power supply command center FAX (16) within a predetermined time, for example, 24 hours. (14) is controlled and an alarm 11 is issued to indicate that the apparatus is in standby for zero output temperature. If it is found that there is no problem within a predetermined time of the countdown by the clock built in the computer (20) and there is no problem, a key for manually inputting the personal identification number (e.g. 29) The alarm 11 is canceled by the input, and the operation is regarded as normal operation, and the process returns to the normal monitoring.
If left unchecked, a signal is sent to the control rod operation handle group (14) to automatically enter the zero output warm state standby state. The image, sound, print display (22) and the release supervisor's cell phone (13) are automatically warned that the reactor manual stop button (15) is pressed within a certain period of time, for example, 48 hours, and the reactor is manually stopped. Issue 12. When the event can be grasped and it is found that there is no problem, the alarm 12 is released by manually inputting the password (29) of the personal identification number notified by the release manager such as the director, but the control rod is removed from the reactor. Preparation for taking out and raising the output is transmitted, and the monitoring ends.
If the reactor is left for more than a predetermined 48 hours, a signal is sent to the reactor manual stop button (15), and the reactor automatically stops. The alarm 13 is transmitted to the image, sound, and print display (22) and the related local governments and the FAX (16). Monitoring ends.
FIGS. 4, 5 and 6 are flowcharts showing the software of the computer (20) of the driving support device of the present invention.
In step {71}, a condition set value used for calculation is input. The allowable range of the measured quantity is determined by the maximum value AU0 and the minimum value AL0. The file name of the computer (20) that stores the measured quantity that is inserted every moment is designated as FILEAI.
Step {72} initializes the value used for the calculation.
NG = 0: Normal state input count.
NR = 0: number of abnormal state inputs. 0 is normal, the blinking of the red lamp has stopped, and the blinking of the green lamp is blinking. Positive indicates an abnormal condition.
NRI1 = 10: Red lamp blinks when NR exceeds NRI1 = 10. The green lamp stops blinking.
NRI2 = 40: An alarm is issued when NR exceeds NRI2 = 40.
TT0 = 200: If NR of NRI2 = 40 or less among TT0 = 200 times including a normal value in the middle from the start of indicating an abnormal state input, it is determined to be an accidental event. The process returns to the initialization of step {72} and is regarded as normal.
H1 = 24: If an event can be grasped within 24 hours after the first alarm is issued and no problem is determined, it is regarded as normal.
H2 = 48: If the event can be grasped within 48 hours after the second alarm is issued and it is determined that there is no problem, it is regarded as normal.
In step {73}, a time Ti used for the calculation is input from a clock built in the computer (20).
In step {74}, the measured amount Ai of the time Ti used for the calculation is input from the FILEAI of the computer (20).
A step {75} discriminates whether or not the measured quantity Ai is within the range between the maximum value AU0 and the minimum value AL0, and if yes, proceeds to step {76}; Proceed to 77｝.
A step {76} calculates a normal state input count NG.
A step {77} calculates an abnormal state input number NR.
A step {78} calculates the total number of inputs TT after indicating the abnormal state.
In a step {79}, it is determined whether or not the abnormal state input number NR is equal to or less than NRI1-1. If the number is less than NRI1-1, the process proceeds to step {80} with YES, and otherwise proceeds to step {81}.
In step {80}, a green lamp blinking switch-on is transmitted to the lamp switch operating device (23) to indicate a steady state. The red lamp goes out.
If NR = 1, NG = 0 is set and the total number of input times TT = NR + NG since the abnormality is first sensed is calculated.
In step {81}, the abnormal state input frequency NR is not equal to or less than NRI1-1 and is NO, and thus the abnormal state is determined. A red lamp blinking switch-on is transmitted to the lamp switch operating device (23) to indicate an abnormal state. The green lamp goes off.
In step {82}, it is determined whether or not the abnormal state input number NR is equal to or more than NRI2 + 1. If it is, the likelihood of the abnormal state increases, and the process proceeds to step {85} with YES, and otherwise proceeds to step {83} with NO. Watch the situation.
In step {83}, it is determined whether or not the total number of inputs TT = NR + NG since the first abnormality is detected is equal to or less than TT0-1. continue. Otherwise, it is determined that it is in a normal state, and the process proceeds to step {84} with NO.
In step {84}, it is determined that the state is normal, and a signal indicating the time Ti and normality is sent to the image, sound, and print display (22). Returning to step {72}, normal monitoring is continued.
In step {85}, a clock built in the computer (20) is initialized and started in order to calculate a time related to the generation of the alarm 11 when the number NR of abnormal state input is equal to or more than NRI2 + 1 and to calculate a time related to the alarm 11 transmission.
In step {86}, a time Tj used for calculation is input from a clock built in the computer (20).
In step {87}, the measured amount Aj of the time Tj is input from FILEAI of the computer (20).
In step {88}, the remaining time HOUR1 is counted down from the maximum remaining time H1 until the next alarm 12.
In step {89}, the computer (20) automatically sends an image, a voice, a print display (22), a release responsible mobile phone (13), and a power supply command office FAX (16). For example, "Alarm 11. Not accidental. Abnormal. Possibility of failure 1.""Detection value Aj.""Prepare control rod insertion within 20 hours. Predict zero output. Check FAX to power supply command center." If the situation can be grasped and there is no problem, the chief of the power station, who has been entrusted by the president and who has full authority, calls the alarm release PIN to the computer (20) and central control room (1) of the present invention. (6) Let's do it "
Step {90} is collation of the release number. If the number is correct, the process proceeds to step {91} with YES, and if not, the process proceeds to step {92} with NO.
In step {91}, since the correct release number has been input from the manual input key (29), it is determined to be normal, and "Release 1" is transmitted to the image, sound, and print display (22). Initialized in step {72}, normal monitoring is continued.
In step {92}, since the situation cannot be grasped, if there is a remaining time HOUR1 until the next stage of the alarm 12, the process returns to step {86} with YES and issues the alarm 11. HOUR1 becomes zero, and the process proceeds to step {93} with NO.
A step {93} initializes and starts a clock built in the computer (20) in order to calculate a time related to the next stage of the alarm 12 transmission.
In step {94}, the time Tk used for the calculation is input from a clock built in the computer (20).
In step {95}, the measured amount Ak of the time Tk is input from the FILEAI of the computer (20).
In the step {96}, the remaining time HOUR2 is counted down from the maximum remaining time H2 until the next alarm 13.
Step {97} is to automatically send a control rod insertion signal, image, sound, print display (22), and release manager from the computer (20) to the control rod operation handles (14) of the plant integrated operation device (3). A warning is sent to the mobile phone (13). For example, "Warning 12. The control rod insertion handle was operated. Zero output but warm standby.""Stop the reactor manually within 36 hours.""If you can grasp the situation and find no problem, entrust the president with full authority. The chief of the cancellation, such as the power plant director, calls the central control room (1) with the PIN for the alarm cancellation (6).
Step {98} is the collation of the release number. If the number is correct, the process proceeds to step {99} with YES, and if not, the process proceeds to step {100} with NO.
In step {99}, since the correct release number has been input from the manual input key (29), it is determined to be normal, and "Release 2" is transmitted to the image, sound, and print display (22). Because the output is zero, "preparation for power increase" is indicated by pulling out the control rod from the reactor. Although it is a standby state at a high temperature and a high pressure even though the output is zero, the return to the steady output can be completed in a single time, but a complicated procedure must be taken. Therefore, the calculation ends at step {100}, and the monitoring ends.
In step {101}, if the situation cannot be grasped and there is a remaining time HOUR2 until the next stage of the alarm 13, the process returns to step {94} with YES and issues the alarm 12. HOUR2 becomes zero, and if NO, the process proceeds to the warning 13 in step {102}.
Step {102} is automatically performed from the computer (20) by pressing a signal for pressing the reactor manual stop button (15) of the plant integrated operation device (3), an image, a sound, a print display (22), and a release-responsible mobile phone ( 13), and send a warning to the relevant local governments and the FAX (12). For example, "Alarm 13. The reactor manual stop button was pressed. Reactor manual stop.""Detection value Ak."
In step {103}, the reactor is manually shut down near room temperature at zero output, so it takes a long time to return to the steady output, and it is necessary to take a complicated procedure. Therefore, the calculation ends and the monitoring ends.
[0006]
【The invention's effect】
Since the present invention hardly changes the conventional plant integrated control device (3), it automatically monitors and determines the abnormality of various equipment of a nuclear power plant without causing a decrease in safety caused by an error caused by construction. By further controlling the furnace power to further improve safety, and automatically issuing warnings to the relevant locations, the notification to the power supply control center FAX (16) improves the reliability of power supply, Reporting to local governments and the regulatory agency FAX (12) will give local residents a sense of security and increase their confidence in nuclear power plants.
In the warm standby state, various inspections become possible, so it is highly likely that the event will be grasped and it is easy to return to normal operation, and in combination with the quick communication with the release manager mobile phone (13), Since meaningless operation stop can be prevented beforehand, the reliability of the nuclear power plant can be improved.
[0007]
[Other Embodiment 1]
As a condition for the abnormality determination, the detection value A (t) of the detector installed on the observation target device is recorded and acquired for a sufficiently long period, for example, 100 hours during the test operation, and the maximum value in that period is set to 1.0 to 2.0. AU0 that is doubled and AL0 whose minimum value is 1.0 to 0.5 times are set as conditions for abnormality determination.
It should be noted that a condition for abnormality determination at an arbitrary output can be obtained by forming a quadratic function of the output from the values of AU0 and AL0 recorded and obtained at 100% output, 75% output, and 50% output.
[0008]
[Other Embodiment 2]
As a condition for the abnormality determination, the detection value A (t) of the detector installed in the observation target device during the test operation is recorded for a sufficiently long period, for example, 100 hours, and an average value A0 per unit time, for example, for 1 minute is obtained. 1.0 to 2.0 times A0 is set as an upper limit value AUM0, and 1.0 to 0.5 times A0 is set as a lower limit value ALM0, which is a condition for abnormality determination.
It should be noted that a condition for determining an abnormality at an arbitrary output can be obtained by forming a quadratic function of the output from the values of AUM0 and ALM0 recorded and acquired at 100% output, 75% output, and 50% output.
[0009]
[Other Embodiment 3]
In addition, in the first and second embodiments, the condition can be updated by recording and acquiring a value after the steady operation after the test operation is started.
[0010]
[Other Embodiment 4]
In addition, as a measuring device (9), a microphone is installed in a machine room (2) of a nuclear reactor or the like, and abnormalities of all devices contained in the machine room (2) of the nuclear reactor or the like are monitored by sound waves. By changing the direction of the directional microphone, the location of the abnormal device is narrowed down.
[0011]
[Other Embodiment 5]
The main measuring device (8) includes a shroud member and a core indicator plate, which are internal structures in a boiling water reactor, and an upper cover, an upper indicator plate, and a lower portion, which are internal structures in a pressurized water reactor. A vibration detector is installed on an indicator plate, a core baffle member, or a heat shield plate to monitor the progress of an existing crack according to the second embodiment, and to monitor the occurrence of a new crack according to the other embodiment 1. Furnace control auxiliary equipment.
The above-mentioned reactor internal structure is not a primary system pressure boundary, and is a structure that does not cause a major problem in reactor safety. However, if left untreated, a serious accident may occur. Since the growth of the existing crack appears as a change in the average vibration smoothly with the passage of time, the growth of the existing crack can be monitored by monitoring the average vibration according to the second embodiment. Since the occurrence of the new crack is suddenly pulse-like, the occurrence of the new crack can be observed by monitoring the instantaneous value according to the first embodiment. By comparing the inspection result of the previous periodic inspection with the inspection result after the end of the monitoring and the monitoring result of the monitoring device, it is possible to obtain a correlation regarding the crack.
[0012]
[Other Embodiment 6]
FIG. 7 is a plan view of the core of the boiling water reactor. The cross-shaped control rods (40) for controlling the reactor power are arranged at a ratio of one to four fuel assemblies (41). At the time of high-power operation, as shown in FIG. 8, every other control rod (40) inserted during operation is inserted. The arrangement in which the control rod (40) can be inserted into the center of the core is called an A pattern, and the other arrangement is called a B pattern. In order to perform the high-power operation in the pattern A, first, all the control rods in the pattern B are pulled out from the core, and then the control rods belonging to the pattern A in the periphery of the core are pulled out from the core. In order to enter the zero-output warm standby state, the control rod (42) to be inserted in the warm standby state is determined in advance from the control rods belonging to the operating pattern, for example, the A pattern, and the control rod operation handle group ( By sending a signal to 14), the insertion control rod (42) for hot standby is inserted, and a zero output hot standby state can be set.
In the manual shutdown of the reactor, all the control rods (40) shown in FIG. 7 are inserted into the core.
[Brief description of the drawings]
FIG. 1 is a block diagram relating to a conventional plant control and monitoring device. FIG. 2 is a block diagram relating to a plant operation support device according to the present invention. FIG. 3 is an overview diagram of a control auxiliary device (11) according to the present invention. FIG. 5 is a flowchart showing software of a computer (20) of the plant operation support apparatus of the invention. FIG. 5 is a continuation of FIG. 4; FIG. 6 is a continuation of FIG. 5; FIG. 8: Example of arrangement of control rods (40) inserted during operation during high-power operation and example of arrangement of control rods (42) to be inserted for warm standby.
1 is a central operation room 2 is a machine room such as a reactor 3 is a plant general control device 4 is a control rod operation handle group 5 is a manual stop button 6 for a reactor 6 is a telephone 7 is a control machine 8 such as a scram 8 is a main measuring device 9 is other measurement The device 10 is a recording device 11 is a control auxiliary device of the present invention 12 is a related local government, a supervisory agency FAX
13 is a person in charge of release, mobile phone 14 is a control rod operation handle group 15 is a reactor manual stop button 16 is a power supply command center FAX
Reference numeral 20 denotes a computer 21; signal transmission / reception control unit 22: image and voice; print display 23: lamp switch operation unit 24: green lamp 25: red lamp 26: measured quantity input device 29: manual input key 40: control rod 41 Is the fuel rod 42, the control rod {71} to {103} for the standby state for warm standby is a flowchart step.

Claims (10)

According to the present invention, a measured amount from a monitoring target device from a main measuring device (8) and other measuring devices (9) in a nuclear power plant is constantly input to a computer (20) via a measured amount input device (26). In this way, it is calculated whether or not the value is within a predetermined value by software built in the signal transmission / reception control unit (21), and if an abnormality is determined, the control rod operation handle group (14) of the plant integrated control device (3) In addition to controlling the reactor power by controlling the reactor manual stop button (15), an image, a sound, a print display (22), a lamp switch operation device (23), an external related local government, a regulatory agency FAX ( 12), the release manager controls the transmission of warnings to the mobile phone (13) and the power supply command center FAX (16) to notify the situation. If the problem is grasped and it is found that there is no problem, the release password is input to the manual input key (29) to return to normal monitoring. If the measured amount is normal, the lamp switch operating device (23) informs that the target device is normal by blinking the green lamp (24), and if abnormal, blinks the red lamp (25) to inform. The present invention is a method and an operation manual document relating to the following driving support in a nuclear power plant. The main measurement quantity and other measurement quantities that do not reach the scrum from the measuring instrument installed on the monitored device are always input to the computer, and the green lamp blinks if there is no abnormality in the monitored device. When the software built into the computer calculates and determines that the measured value is abnormal, the green lamp goes out and the red lamp blinks. If it is determined that the abnormality is completed in a short time and it is accidental, the blinking of the red lamp is turned off and the green lamp is blinked again. If the abnormality progresses, an image, sound, and print warning are sent to the person in charge of release and the power supply command center FAX to control the control rod operation handle group within a certain period of time, for example, 24 hours, and to wait for zero output warm state. Emits on the display. If the event can be grasped within a predetermined time and it is found that there is no problem, the alarm is canceled by manually inputting the personal identification number notified by the manager in charge of cancellation such as the director and the operation is regarded as normal operation and the operation returns to the normal monitoring. If left unattended, a warning is issued on the image, sound, and print display to the release manager's mobile phone by pressing the reactor manual stop button within a certain period of time, for example, 48 hours, to stop the reactor manually. If the event can be grasped and there is no problem, the alarm is released by manual key input of the PIN issued by the director in charge of release, such as the director, but the output is increased by removing the control rod from the reactor The preparation is sent and the monitoring ends. If the reactor has been left for more than a predetermined 48 hours, a warning is issued to press the reactor manual stop button to stop the reactor manually. Monitoring ends. As a condition for the abnormality determination in claims 1 and 2, a detection value A (t) of a detector installed on the observation target device is recorded and acquired during the test operation, and the maximum value in the period is set to 1.0 to 2 AU0 that has been increased by a factor of 0.0 and AL0 whose minimum value has been increased by a factor of 1.0 to 0.5 are set as conditions for abnormality determination.
It should be noted that a condition for determining an abnormality at an arbitrary output is obtained by forming a quadratic function of the output from the values of AU0 and AL0 recorded and obtained at the 100% output, the 75% output, and the 50% output. As conditions for the abnormality determination in claims 1 and 2, a detection value A (t) of a detector installed in the observation target device is recorded and acquired during the test operation, and an average value A0 per unit time is obtained. 1.0 to 2.0 times the upper limit value AUM0 and 1.0 to 0.5 times A0 as the lower limit value ALM0, which are the conditions for abnormality determination.
It should be noted that the condition of the abnormality determination at an arbitrary output is determined by making a quadratic function of the output from the values of AUM0 and ALM0 recorded and acquired at 100% output, 75% output, and 50% output. In the third and fourth aspects, the condition for abnormality determination is updated by recording and acquiring a value obtained after the steady operation after the test operation is started. In Claims 1 and 2, a microphone is installed in a machine room (2) such as a reactor as the other measuring device (9), and abnormalities of all the devices stored in the machine room (2) such as the reactor are detected by sound waves. Monitor. The location of the abnormal device is narrowed down by changing the direction of the directional microphone. 3. A shroud member and a core indicator plate which are internal structures in a boiling water reactor as a main measuring device (8), and a reactor vessel which is an internal structure in a pressurized water reactor according to claim 1 or 2. By installing a vibration detector on the upper lid, the upper indicator, the lower indicator, the core baffle member and the heat shield, the progress of an existing crack is monitored by claim 4, and the occurrence of a new crack is monitored by claim 3. . 8. The correlation according to claim 7, wherein the correlation between the previous periodic inspection and the inspection and inspection result after the end of the monitoring and the monitoring result by the monitoring device are compared. 3. The control rod (42) according to claim 1 or 2, wherein the hot-water standby insertion planned control rod (42) for bringing the boiling water reactor into a zero-output hot standby state is a control rod belonging to the operating pattern. In claim 1 and claim 2, when the number of abnormal state inputs exceeds a set value, a blinking switch-on is transmitted to a red lamp (25) to indicate an abnormal state. An alarm is issued when the total number of inputs after the first detection of an abnormality is equal to or less than the set value and the number of abnormal state inputs is about twice or more the initial set value. If the total number of inputs after the first detection of the abnormality is equal to or greater than the set value and the number of abnormal state inputs is less than about twice the initial set value, it is regarded as normal and the green lamp (24) blinks.

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