CN110448844A - The synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station - Google Patents
The synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station Download PDFInfo
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- CN110448844A CN110448844A CN201910630502.5A CN201910630502A CN110448844A CN 110448844 A CN110448844 A CN 110448844A CN 201910630502 A CN201910630502 A CN 201910630502A CN 110448844 A CN110448844 A CN 110448844A
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- A—HUMAN NECESSITIES
- A62—LIFE-SAVING; FIRE-FIGHTING
- A62C—FIRE-FIGHTING
- A62C35/00—Permanently-installed equipment
- A62C35/58—Pipe-line systems
- A62C35/68—Details, e.g. of pipes or valve systems
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Abstract
The present invention relates to nuclear power station fire water productions and distribution system technical field, a kind of synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station is provided, is connected comprising steps of fire water pump group is exported the external extinguishing pipe on contact pipeline using master's interim pipeline with the external fire-fighting head on a set of host fire_fighting pipe network;At least one exhaust pipe on host fire_fighting pipe network to peripheral fire_fighting pipe network is connected into power station compression gas pipe;By isolating valve isolation each on each host fire_fighting pipe network to the peripheral fire_fighting pipe network;Each isolating valve is replaced, the isolation to each isolating valve is gradually released;Remove main interim pipeline.Host fire_fighting pipe network can be quickly discharged to the water in the pipeline of peripheral fire_fighting pipe network in the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station of the present invention, and then improve the replacement efficiency of each isolating valve on the pipeline, shorten replacing construction, and it can guarantee host fire_fighting pipe network fire water, to guarantee Steam Turbine system safety operation, security risk is reduced.
Description
Technical field
The invention belongs to nuclear power station fire water productions and distribution system technical field, are to be related to a seed nucleus more specifically
The synchronous method for replacing peripheral workshop fire-fighting water isolation valve in power station.
Background technique
The fuel that nuclear power station uses risk with higher;Thus, in nuclear power station operation, need good and steady
Surely it ensures and safeguards.This just needs good fire-fighting system, with ensure nuclear power station generating set and corollary equipment ground it is good
Good luck row and at any time solution of emergent event guarantee personnel safety.And due to early stage nuclear power station, generally comprise two steam turbine systems
System, peripheral auxiliary system and auxiliary corollary system corresponding with each Steam Turbine system;Each Steam Turbine system includes steamer
Unit, main transformer and plant area's transformer room equipment and device;Peripheral auxiliary system includes auxiliary transformer and water charging system etc.
Equipment and device;And it assists corollary system to generally comprise auxiliary feedwater system, diesel engine, electrical equipment, reactor system etc. and sets
Standby and device.Correspondingly, the fire-fighting system of nuclear power station needs to cover two Steam Turbine systems, peripheral auxiliary system and auxiliary
Corollary system.In addition, ensureing to increase, the fire_fighting pipe network for covering peripheral auxiliary system generally can also be connected to the core of other phases
Power station.Thus, the fire-fighting system of nuclear power station be it is extremely complex, design, manufacture it is larger with management difficulty, need a large amount of people
Member's maintenance, to guarantee the normal operation of nuclear power station.And it since nuclear power station fire_fighting pipe network system is before implementation, that is, is setting
Meter, simulation and verifying, exactly concentrate a large amount of industry specialists to be investigated, then prove, are then designed, in design, one
As be by multiple stability simulation test, emergency situations simulation test, also to be verified later, expert's audit etc. it is stringent
Process;Its each process before implementing has concentrated the labour, certification and examination of a large amount of experts, thus nuclear power station extinguishing pipe
Net system design, simulation with verifying after, with guarantee fire-fighting system can in time and operate normally, can just implement.This is allowed for
The fire-fighting system of nuclear power station is once designing and verifying, and often suitability use is in more phase nuclear power stations.Current nuclear power station fire-fighting
System generally comprise two sets of fire water pump groups, the host fire_fighting pipe network for being covered each by each Steam Turbine system, be covered each by it is each auxiliary
It helps the mating fire_fighting pipe network of corollary system and covers the peripheral fire_fighting pipe network of peripheral auxiliary system.Fire water from fire water pump group to
Host fire_fighting pipe network, then to peripheral fire_fighting pipe network after depressurizing.
In fire_fighting pipe network normal use, the state of valve is usually and will not change in pipe network, i.e., normally opened valve meeting one
It is straight normally opened, and normally closed valve can be always it is normally closed, thus, valve is usually the problems such as being not in interior leakage.However, certain core
Power station can often disappear in the operation by long-term (being up to 10 years) since nuclear power station needs that good fire-fighting is kept to guard
Anti- manoeuvre, and in manoeuvre, usually progress fire water zone isolation makes winner that is, by different workshop progress subregion isolation
Machine fire_fighting pipe network needs continually to switch operation to the isolating valve between peripheral fire_fighting pipe network on pipeline, this results in these isolation
Valve, the easily interior leakage of other valves relatively in nuclear power station fire_fighting pipe network system.When on host fire_fighting pipe network to peripheral fire_fighting pipe network
Can have leakage, the equipment annual overhaul that will lead in peripheral auxiliary system in multiple isolating valves can not carry out.And if will be more
These isolating valves are changed, since host fire_fighting pipe network is big to the pipe diameter between peripheral fire_fighting pipe network, pressure is higher, general diameter exists
300mm or more, for pressure in 12bar, pipeline is longer, to guarantee that hydraulic pressure in pipeline is released in security needs, causes using pipe
Drain valve water discharge time is too long on road, easily leads to host fire_fighting pipe network and loses fire water for a long time, and seriously threatens unit safety.
Summary of the invention
The purpose of the present invention is to provide a kind of synchronous methods for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station, with solution
It is leaked in multiple isolating valves on host fire_fighting pipe network to peripheral fire_fighting pipe network in nuclear power station fire-fighting system certainly existing in the prior art
Afterwards, it is difficult to the problem of replacing, seriously threatening unit safety.
To achieve the above object, the technical solution adopted by the present invention is that: provide that a kind of nuclear power station is synchronous to replace peripheral workshop
The method of fire-fighting water isolation valve, includes the following steps:
Preparation stage: fire water pump group is exported into the external extinguishing pipe got in touch on pipeline and a set of master using main interim pipeline
External fire-fighting head on machine fire_fighting pipe network is connected;By at least one on the host fire_fighting pipe network to the peripheral fire_fighting pipe network
Exhaust pipe connects power station compression gas pipe;
Block isolation: each isolating valve on each host fire_fighting pipe network to the peripheral fire_fighting pipe network is isolated;
Sessions: opening the drain valve on the host fire_fighting pipe network to the peripheral fire_fighting pipe network on each drainpipe,
The exhaust valve on the exhaust pipe and the supplying compressed gas into the exhaust pipe are opened, until the drained host fire_fighting pipe network
To the water in the pipeline of the peripheral fire_fighting pipe network;It replaces again each on the host fire_fighting pipe network to the peripheral fire_fighting pipe network
Isolating valve;
Restoration stage: it opens at least one exhaust pipe on the host fire_fighting pipe network to the peripheral fire_fighting pipe network
Exhaust valve closes each drain valve on the host fire_fighting pipe network to the peripheral fire_fighting pipe network;It gradually releases to the host
The isolation of each isolating valve on fire_fighting pipe network to the peripheral fire_fighting pipe network, to disappear to the host fire_fighting pipe network to the periphery
It water-filling and is vented in the pipeline of anti-pipe network;
It fulfils assignment: removing the connection of the interim pipeline of the master and the disconnection exhaust pipe and the power station compression gas pipe.
Further, the block isolation step specifically includes:
First isolation block: it will be closed in each host fire_fighting pipe network to the valve of the peripheral fire_fighting pipe network;
Second isolation block: the valve in the fire water pump group to each host fire_fighting pipe network is closed;
Block is isolated in third: each isolation before each host fire_fighting pipe network will be connected in the peripheral fire_fighting pipe network
Valve is closed.
Further, the Restoration stage step further include:
It gradually opens in each host fire_fighting pipe network to the valve of the peripheral fire_fighting pipe network, with to the host fire-fighting
Pipe network water-filling and is vented into the pipeline of the peripheral fire_fighting pipe network, and when water being discharged in the open exhaust pipe, closing should
Exhaust pipe is further continued for opening to the valve of the peripheral fire_fighting pipe network in each host fire_fighting pipe network, until the host disappears
Anti- pipe network hydraulic pressure into the pipeline of the peripheral fire_fighting pipe network is consistent with hydraulic pressure in the host fire_fighting pipe network.
Further, the preparation stage step further include will be on the host fire_fighting pipe network to the peripheral fire_fighting pipe network
Multiple exhaust pipes be separately connected power station compression gas pipe.
Further, it is further comprised the steps of: after the preparation stage
Emergency response: fire brigade original place is guarded, and special messenger is allowed to carry out live inspection, until the step that fulfils assignment;
Described fulfil assignment after step further includes that notice fire brigade drops one's guard step.
Further, fire-fighting warning is further comprised the steps of: before the emergency response step: notice fire brigade guards.
Further, it is further comprised the steps of: before the emergency response step
Operation warning: forbid each Steam Turbine system corresponding region and peripheral auxiliary system corresponding region fire operation;
It further include releasing to forbid each Steam Turbine system corresponding region and periphery auxiliary system after the step that fulfils assignment
The step of system corresponding region fire operation.
Further, the preparation stage step further include: connect in the interim pipeline of the master with the external extinguishing pipe
Place's setting protective fence, and protective fence is set in the interim pipeline of the master and the external fire-fighting head junction.
Further, the step that fulfils assignment further include: further include removing institute before removing the interim pipeline of master
The step of stating protective fence.
Further, the preparation stage step further include: setting is for being discharged the temporary drainage pump of water in draining melt pit;
The step that fulfils assignment further include: remove the temporary drainage pump.
Further, the temporary drainage pump is set to the pipeline on the host fire_fighting pipe network to the peripheral fire_fighting pipe network
Corresponding region.
Further, the temporary drainage pump is set on the host fire_fighting pipe network to the peripheral fire_fighting pipe network and respectively drains
Manage corresponding position.
Further, it is further comprised the steps of: before the preparation stage step
Time is selected: selecting a set of Steam Turbine and carries out large repairs.
Further, it is further comprised the steps of: before the block isolation step
Overhaul is shut down: the Steam Turbine to overhaul being completed reactor core complete unloading operating condition, and the Steam Turbine is corresponding
Main transformer is stopped transport.
Further, it is further comprised the steps of: before the block isolation step, after Yu Suoshu overhaul outage
Evacuation procedure: oil, hydrogen in conventional island are emptied.
Further, the preparation stage step further includes transporting new valve at the corresponding isolating valve to be replaced.
Further, the preparation stage step further includes the movable stand that setting supports each new valve respectively, and is made
The height and position phase of each flange hole is corresponded on each new valve on each flange hole height and position and the isolating valve to be replaced
Together.
Further, the preparation stage step further include set up at each isolating valve to be replaced support frame and
Rope is bound on each isolating valve to be replaced, chain block is set on support frame as described above, by the chain block
Chain suspension hook be connected with the rope.
Further, the completion stage further includes removing each support frame as described above.
The beneficial effect of the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station provided by the invention is: with
The prior art is compared, by the present invention in that with the pipeline and host fire_fighting pipe network phase that interim pipeline exports fire water pump group is led
Even;To after each isolating valve on host fire_fighting pipe network to peripheral fire_fighting pipe network is isolated, it is ensured that host fire-fighting
Pipe network has fire water, to guarantee Steam Turbine system safety operation, reduces security risk;And by host fire_fighting pipe network
To high pressure gas is sent in exhaust pipe on pipe network between peripheral fire_fighting pipe network, to accelerate drainage speed in the pipe network, may be implemented half
Draining is completed in hour, compared to nearly 20 hours water discharge times are currently needed, is substantially shortened, and it is hidden to greatly reduce safety
Suffer from, and then each isolating valve on host fire_fighting pipe network to peripheral fire_fighting pipe network can be replaced.
Detailed description of the invention
It to describe the technical solutions in the embodiments of the present invention more clearly, below will be to embodiment or description of the prior art
Needed in attached drawing be briefly described, it should be apparent that, the accompanying drawings in the following description is only of the invention some
Embodiment for those of ordinary skill in the art without creative efforts, can also be attached according to these
Figure obtains other attached drawings.
Fig. 1 is the process of the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station provided in an embodiment of the present invention
Schematic diagram;
Fig. 2 is nuclear power station fire-fighting system pipeline architecture flow diagram provided in an embodiment of the present invention.
Wherein, each attached drawing main mark in figure:
11- fire water pump group;12- water main line;121- zone isolation valve;122- workshop isolating valve;13- gets in touch with pipeline;
131- gets in touch with isolating valve;The external extinguishing pipe of 14-;The external isolating valve of 141-;
20- host fire_fighting pipe network;21- control valve;22- connection pipeline;221- connection isolating valve;The external fire-fighting head of 23-;
24- exhaust pipe;241- exhaust valve;
The periphery 30- fire_fighting pipe network;31- separated time pipeline;311- separated time isolating valve;32- doubling pipeline;321- doubling isolation
Valve;33- by-pass line;331- bypass isolation valves;34- drainpipe;341- drain valve;The periphery 35- isolating valve;
The mating fire_fighting pipe network of 40-;41- assists supporting pipelines;The interim pipeline of 61- master.
Specific embodiment
In order to which technical problems, technical solutions and advantages to be solved are more clearly understood, tie below
Accompanying drawings and embodiments are closed, the present invention will be described in further detail.It should be appreciated that specific embodiment described herein is only
To explain the present invention, it is not intended to limit the present invention.
It should be noted that it can be directly another when element is referred to as " being fixed on " or " being set to " another element
On one element or indirectly on another element.When an element is known as " being connected to " another element, it can
To be directly to another element or be indirectly connected on another element.
In addition, term " first ", " second " are used for descriptive purposes only and cannot be understood as indicating or suggesting relative importance
Or implicitly indicate the quantity of indicated technical characteristic.Define " first " as a result, the feature of " second " can be expressed or
Implicitly include one or more of the features.In the description of the present invention, the meaning of " plurality " is two or more,
Unless otherwise specifically defined." several " are meant that one or more, unless otherwise specifically defined.
In the description of the present invention, it is to be understood that, term " center ", " length ", " width ", " thickness ", "upper",
The orientation or position of the instructions such as "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outside"
Relationship is to be based on the orientation or positional relationship shown in the drawings, and is merely for convenience of description of the present invention and simplification of the description, without referring to
Show or imply that signified device or element must have a particular orientation, be constructed and operated in a specific orientation, therefore cannot manage
Solution is limitation of the present invention.
In the description of the present invention, it should be noted that unless otherwise clearly defined and limited, term " installation ", " phase
Even ", " connection " shall be understood in a broad sense, for example, it may be being fixedly connected, may be a detachable connection, or be integrally connected;It can
To be mechanical connection, it is also possible to be electrically connected;It can be directly connected, can also can be indirectly connected through an intermediary
The interaction relationship of connection or two elements inside two elements.It for the ordinary skill in the art, can be with
The concrete meaning of above-mentioned term in the present invention is understood as the case may be.
Fig. 1 and Fig. 2 is please referred to, the side for replacing peripheral workshop fire-fighting water isolation valve now synchronous to nuclear power station provided by the invention
Method is illustrated.The synchronous method for replacing peripheral workshop fire-fighting water isolation valve of the nuclear power station, includes the following steps:
Preparation stage S1: fire water pump group 11 is exported to the external extinguishing pipe got in touch on pipeline 13 using main interim pipeline 61
14 are connected with the external fire-fighting head 23 on a set of host fire_fighting pipe network 20;It will be on host fire_fighting pipe network 20 to peripheral fire_fighting pipe network 30
At least one exhaust pipe 24 connect power station compression gas pipe;
S4 is isolated in block: each isolating valve on each host fire_fighting pipe network 20 to the peripheral fire_fighting pipe network 30 is isolated;
Sessions S5: it opens on the host fire_fighting pipe network 20 to the peripheral fire_fighting pipe network 30 on each drainpipe 34
Drain valve 341 opens the exhaust valve 241 on the exhaust pipe 24 and the supplying compressed gas into the exhaust pipe 24, until row
The complete host fire_fighting pipe network 20 is to the water in the pipeline of the peripheral fire_fighting pipe network 30;The host fire_fighting pipe network 20 is replaced again
Each isolating valve onto the peripheral fire_fighting pipe network 30;
Restoration stage S6: it opens described at least one on the host fire_fighting pipe network 20 to the peripheral fire_fighting pipe network 30
Exhaust valve 241 on exhaust pipe 24 closes each row on the host fire_fighting pipe network 20 to the peripheral fire_fighting pipe network 30
Water valve 341;The isolation to each isolating valve on the host fire_fighting pipe network 20 to the peripheral fire_fighting pipe network 30 is gradually released, with
It water-filling and is vented to the host fire_fighting pipe network 20 into the pipeline of the peripheral fire_fighting pipe network 30;
Fulfil assignment S7: removing the interim pipeline 61 of the master and disconnects the exhaust pipe 24 and the power station compression gas pipe
Connection.
By above-mentioned preparation stage S1 step, the interim pipeline 61 of master can be connected in advance, disappeared with reducing replacement periphery
The time of isolating valve on anti-pipe network 30, i.e. reduction activity duration, and then reduce risk.Using the interim pipeline 61 of master by fire pump
External extinguishing pipe 14 on 11 outlet contact pipeline 13 of group is connected with the external fire-fighting head 23 on a set of host fire_fighting pipe network 20;When
When valve between fire water pump group 11 and host fire_fighting pipe network 20 is closed, still it can be disappeared by fire water pump group 11 to host
Anti- pipe network 20 provides fire water, to guarantee the security against fire of Steam Turbine devices in system operation.By host fire_fighting pipe network 20
At least one exhaust pipe 24 on to peripheral fire_fighting pipe network 30 connects power station compression gas pipe, to facilitate to the host fire_fighting pipe network
20 are filled with compressed gas into the pipeline of the peripheral fire_fighting pipe network 30, so that host can quickly be discharged in sessions S5
Fire_fighting pipe network 20 is to the water in the pipeline of peripheral fire_fighting pipe network 30.
S4 step is isolated by above-mentioned block, between host fire_fighting pipe network 20 to each isolating valve peripheral fire_fighting pipe network 30
It is isolated, to replace these valves.
In above-mentioned Restoration stage S6 step, since host fire_fighting pipe network 20 is higher to 30 pressure of peripheral fire_fighting pipe network,
Generally 12bar or so gradually releases the isolation of each isolating valve arriving peripheral fire_fighting pipe network 30 to host fire_fighting pipe network 20, can
So that host fire_fighting pipe network 20 is gradually recovered pressure to the pipeline between peripheral fire_fighting pipe network 30, safeguard protection can be played the role of,
Reduce the impact to pipeline.And at least one exhaust pipe 24 on host fire_fighting pipe network 20 to peripheral fire_fighting pipe network 30 is opened, with
Just the gas into the pipe network of peripheral fire_fighting pipe network 30 of host fire_fighting pipe network 20 is quickly discharged.
The synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station provided by the invention, compared with prior art,
By the present invention in that the pipeline that fire water pump group 11 exports is connected with host fire_fighting pipe network 20 with main interim pipeline 61, thus
After each isolating valve on host fire_fighting pipe network 20 to peripheral fire_fighting pipe network 30 is isolated, it is ensured that host fire_fighting pipe network 20
Security risk is reduced to guarantee Steam Turbine system safety operation with fire water, by arriving periphery to host fire_fighting pipe network 20
It is sent to high pressure gas in exhaust pipe 24 on 30 pipe networks of fire_fighting pipe network, is arrived between peripheral fire_fighting pipe network 30 with accelerating host fire_fighting pipe network 20
The drainage speed of pipe network may be implemented to complete draining within half an hour, compared to nearly 20 hours water discharge times are currently needed, obtain
To substantially shortening, security risk is greatly reduced, and then can be to each on host fire_fighting pipe network 20 to peripheral fire_fighting pipe network 30
Isolating valve is replaced.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, nuclear power station fire-fighting system include two sets of fire water pump groups 11, are covered each by respectively
The host fire_fighting pipe network 20 of Steam Turbine system, the mating fire_fighting pipe network 40 for being covered each by each auxiliary corollary system and covering periphery
The peripheral fire_fighting pipe network 30 of auxiliary system.The outlet of two sets of fire water pump groups 11 passes through water main line 12 respectively and is connected to two sets of masters
Machine fire_fighting pipe network 20.Two sets of water main lines 12 are in parallel by contact pipeline 13;It gets in touch on pipeline 13 close to each set fire water pump group
11 position, which is respectively equipped with, gets in touch with isolating valve 131, and there are external extinguishing pipe 14, external extinguishing pipes between two contact isolating valves 131
14 are equipped with external isolating valve 141.Each water main line 12 is equipped with the auxiliary extended to corresponding mating fire_fighting pipe network 40 and matches casing
Line 41.Two sets of host fire_fighting pipe networks 20 are connected to by connection pipeline 22, and connection pipeline 22 is equipped with connection isolating valve 221, connection
Isolating valve 221 is equipped with external fire-fighting head 23.Workshop is equipped with before reaching respective host fire_fighting pipe network 20 on each water main line 12
Isolating valve 122, and zone isolation valve 121 is equipped with before reaching workshop isolating valve 122 on water main line 12.Each set host fire-fighting
The separated time pipeline 31 for being respectively communicated with peripheral fire_fighting pipe network 30 is led on pipe network 20, two separated time pipelines 31 pass through doubling pipeline 32
Connection, each doubling pipeline 32 are respectively equipped with doubling isolating valve 321, two doubling isolating valves close to the position of each separated time pipeline 31
The by-pass line 33 being connected to peripheral fire_fighting pipe network 30 is connected on doubling pipeline 32 between 321, by-pass line 33 is equipped with
Bypass isolation valves 331.It is additionally provided with separated time isolating valve 311 before to peripheral fire_fighting pipe network 30 on each separated time pipeline 31.Peripheral fire-fighting
Pipe network 30 is equipped with peripheral isolating valve 35 before being connected to each separated time pipeline 31;And each separated time pipeline 31 is respectively equipped with drainpipe 34,
Each drainpipe 34 is equipped with drain valve 341;It is respectively equipped with exhaust pipe 24 on host fire_fighting pipe network 20 and separated time pipeline 31, it is each to be vented
Pipe 24 is equipped with exhaust valve 241.
It is using the interim pipeline 61 of master by external extinguishing pipe 14 and external fire-fighting head 23 then in above-mentioned preparation stage S1 step
It is connected.
In the present embodiment, two doubling isolating valves, 321, two separated time isolating valves 311 need replacing simultaneously.At some other
In embodiment, two or more hairs in two doubling isolating valves, 321, two separated time isolating valves 311 and two bypass isolation valves 331
Raw leakage can be using the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station of the present embodiment when needing replacing.
I.e. two doubling isolating valves, 321, two separated time isolating valves 311 and bypass isolation valves 331 are that host fire_fighting pipe network 20 disappears to periphery
Isolating valve on anti-pipe network 30.Above-mentioned block isolation S4 is then actually that these valves are isolated.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the block isolation S4 step specifically include:
First isolation block S41: it will be closed in each host fire_fighting pipe network 20 to the valve of the peripheral fire_fighting pipe network 30
It closes;
Second isolation block S42: the valve in the fire water pump group 11 to each host fire_fighting pipe network 20 is closed;
Block S43 is isolated in third: will be connected to before each host fire_fighting pipe network 20 in the peripheral fire_fighting pipe network 30
Each separation valve door close.
By above-mentioned first isolation block S41 step, enter peripheral extinguishing pipe to prevent fire water in host fire_fighting pipe network 20
Net 30.By above-mentioned second isolation block S42 step, is directed out to prevent fire water pump group 11 and enclose the supply fire-fighting of fire_fighting pipe network 30
Water.Block S43 step is isolated by above-mentioned third, each isolating valve is flowed backward to prevent fire water in peripheral fire_fighting pipe network 30, with more
The fast host fire_fighting pipe network 20 that is discharged is to the water in the pipeline of peripheral fire_fighting pipe network 30.
Specifically, actually each workshop isolating valve 122 is closed in above-mentioned first isolation block S41 step.It preferentially, can be with
Each zone isolation valve 121 is closed simultaneously, to improve isolation effect.Actually by each set in above-mentioned second isolation block S42 step
It is closed in host fire_fighting pipe network 20 to the control valve 21 of corresponding separated time pipeline 31.It is practical in above-mentioned third isolation block S43 step
A forward bypass isolation valves 331 and each peripheral isolating valve 35 are closed.To realize two doubling isolating valve 321, two
Separated time isolating valve 311 is isolated.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the Restoration stage S6 step further include:
It gradually opens in each host fire_fighting pipe network 20 to the valve of the peripheral fire_fighting pipe network 30, with to the host
Fire_fighting pipe network 20 water-filling and is vented into the pipeline of the peripheral fire_fighting pipe network 30, and water is discharged in the open exhaust pipe 24
When, the exhaust pipe 24 is closed, is further continued for opening in each host fire_fighting pipe network 20 to the valve of the peripheral fire_fighting pipe network 30,
Until the host fire_fighting pipe network 20 is into the pipeline of the peripheral fire_fighting pipe network 30 in hydraulic pressure and the host fire_fighting pipe network 20
Hydraulic pressure is consistent.To improve safety.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, in above-mentioned Restoration stage S6 step, specifically, opened areas isolating valve 121,
A workshop isolating valve 122 is gradually opened again, fire water is filled with into separated time pipeline 31 and doubling pipeline 32, in open exhaust
When water being discharged in pipe 24, the exhaust pipe 24 is closed;It is further continued for opening the workshop isolating valve 122, until separated time pipeline 31 and doubling
Hydraulic pressure is consistent with hydraulic pressure in water main line 12 in pipeline 32.It is then turned in each set host fire_fighting pipe network 20 to corresponding separated time pipeline 31
Control valve 21, bypass isolation valves 331 and each peripheral isolating valve 35.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the preparation stage S1 are further comprised the steps of: later
Emergency response F2: fire brigade original place is guarded, and special messenger is allowed to carry out live inspection, until the S7 step that fulfils assignment
Suddenly;By the setting of emergency response F2 step, emergency fire-fighting can be made in advance and is prepared, preferably guarantees security against fire.
Described fulfil assignment after S7 step further includes that notice fire brigade drops one's guard step.So as in the S7 step that fulfils assignment
After rapid, cancel emergency fire-fighting, reduce the working strength of personnel.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the emergency response F2 step further comprise the steps of: fire-fighting warning F11 before:
Fire brigade is notified to guard., before, fire brigade to be made to get ready, to improve efficiency in block isolation S4 step, reduce operation
Time.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the emergency response F2 step further comprise the steps of: before
F12 is guarded against in operation: forbidding each Steam Turbine system corresponding region and peripheral auxiliary system corresponding region fire operation;
To reduce the security risk during replacing isolating valve operation.
It further include releasing to forbid each Steam Turbine system corresponding region and periphery auxiliary after the S7 step that fulfils assignment
The step of system corresponding region fire operation.After the S7 that fulfils assignment, restore the normal operation and work of personnel.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the preparation stage S1 step further include: the interim pipeline of the master 61 with
Protective fence is arranged in 14 junction of external extinguishing pipe, and in the interim pipeline 61 of the master and external 23 junction of fire-fighting head
Protective fence is set.Protective fence is set, preferably to be reminded and be protected, reduces hidden danger.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the S7 step that fulfils assignment further include: removing the interim pipeline of master
Further include the steps that removing the protective fence before 61.To facilitate postorder operation, convenient for restoring normal operation.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the preparation stage S1 step further include: setting is for being discharged draining melt pit
The temporary drainage of middle water pumps;
The S7 step that fulfils assignment further include: remove the temporary drainage pump.
Due to needing to be discharged corresponding pipeline when replacing the isolating valve on host fire_fighting pipe network 20 to peripheral fire_fighting pipe network 30
In fire water, and temporary drainage pump is set, can drain faster, improve safety and operating efficiency.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the temporary drainage pump are set to the host fire_fighting pipe network 20 and arrive the periphery
The corresponding region of pipeline on fire_fighting pipe network 30.Quickly to be drained, improve efficiency.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the temporary drainage pump are set to the host fire_fighting pipe network 20 and arrive the periphery
The corresponding position of each drainpipe 34 is improved efficiency on fire_fighting pipe network 30 with quickly draining, and shortens water discharge time.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the preparation stage S1 step further comprise the steps of: before
Time selectes S0: selecting a set of Steam Turbine and carries out large repairs.The time that a set of Steam Turbine carries out large repairs is selected, by
In in overhaul, the Steam Turbine and corresponding nuclear island, main transformer and ancillary equipment can stop working, then can reduce to vapour
The influence of unit is taken turns, and reduces security risk.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the block isolation S4 step further comprise the steps of: before
S2 is shut down in overhaul: the Steam Turbine to overhaul being completed reactor core complete unloading operating condition, and the Steam Turbine is corresponding
Main transformer stop transport.S2 step is shut down by overhaul, security risk can be further decreased.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, before block isolation S4 step, Yu Suoshu overhaul shut down S2 step it
After further comprise the steps of:
Evacuation procedure S3: oil, hydrogen in conventional island are emptied.
By above-mentioned evacuation procedure S3, fire risk can be reduced 50%, improve safety.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the preparation stage S1 step further include that new valve transport correspondence is to be replaced
The isolating valve at, thus after isolating valve to be replaced under disassembly, new valve can be installed as early as possible, when shortening replacement valve
Between, it improves efficiency, reduces security risk.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the preparation stage S1 step further include that setting supports each new valve respectively
The movable stand of door, and make to correspond to each flange on each flange hole height and position and the isolating valve to be replaced on each new valve
The height and position in hole is identical.It due to new valve heavier-weight, is moved using movable stand, personnel labor intensity can be reduced, and
And can quickly be mounted on pipeline, it improves efficiency, shortens replacement valve times, reduce security risk.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the preparation stage S1 step further include in each isolating valve to be replaced
Place sets up support frame and binds rope on each isolating valve to be replaced, and setting pulls calabash on support frame as described above
The chain suspension hook of the chain block is connected by reed with the rope.Since isolating valve to be replaced is heavier, and it is to be replaced every
It is stronger from valve fixation, and support frame and chain block are set, it is convenient when dismantling isolating valve to be replaced, it loosens to be replaced
Isolating valve, and after removal, the isolating valve is removed, installation new valve is facilitated, to improve efficiency, shortens replacement valve times, drop
Lower security risk.
Further, Fig. 1 to Fig. 2 is please referred to, as the peripheral workshop fire water of the synchronous replacement of nuclear power station provided by the invention
A kind of specific embodiment of the method for isolating valve, the completion stage S7 further includes removing each support frame as described above, so as to the later period
Operate the valve.
The foregoing is merely illustrative of the preferred embodiments of the present invention, is not intended to limit the invention, all in essence of the invention
Made any modifications, equivalent replacements, and improvements etc., should all be included in the protection scope of the present invention within mind and principle.
Claims (19)
1. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station, characterized by the following steps:
Preparation stage: fire water pump group is exported into the external extinguishing pipe on contact pipeline using master's interim pipeline and is disappeared with a set of host
External fire-fighting head on anti-pipe network is connected;By at least one exhaust on the host fire_fighting pipe network to the peripheral fire_fighting pipe network
Pipe connects power station compression gas pipe;
Block isolation: each isolating valve on each host fire_fighting pipe network to the peripheral fire_fighting pipe network is isolated;
Sessions: the drain valve on the host fire_fighting pipe network to the peripheral fire_fighting pipe network on each drainpipe is opened, is opened
Exhaust valve on the exhaust pipe and the supplying compressed gas into the exhaust pipe, up to the drained host fire_fighting pipe network to institute
State the water in the pipeline of peripheral fire_fighting pipe network;Each isolation on the host fire_fighting pipe network to the peripheral fire_fighting pipe network is replaced again
Valve;
Restoration stage: the exhaust at least one exhaust pipe on the host fire_fighting pipe network to the peripheral fire_fighting pipe network is opened
Valve closes each drain valve on the host fire_fighting pipe network to the peripheral fire_fighting pipe network;It gradually releases to the host fire-fighting
The isolation of each isolating valve on pipe network to the peripheral fire_fighting pipe network, to the host fire_fighting pipe network to the periphery extinguishing pipe
It water-filling and is vented in the pipeline of net;
It fulfils assignment: removing the connection of the interim pipeline of the master and the disconnection exhaust pipe and the power station compression gas pipe.
2. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as described in claim 1, it is characterised in that: institute
Block isolation step is stated to specifically include:
First isolation block: it will be closed in each host fire_fighting pipe network to the valve of the peripheral fire_fighting pipe network;
Second isolation block: the valve in the fire water pump group to each host fire_fighting pipe network is closed;
Block is isolated in third: each separation valve door before each host fire_fighting pipe network will be connected in the peripheral fire_fighting pipe network
It closes.
3. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as claimed in claim 2, it is characterised in that: institute
State Restoration stage step further include:
It gradually opens in each host fire_fighting pipe network to the valve of the peripheral fire_fighting pipe network, with to the host fire_fighting pipe network
It water-filling and is vented into the pipeline of the peripheral fire_fighting pipe network, when water being discharged in the open exhaust pipe, closes the exhaust
Pipe is further continued for opening to the valve of the peripheral fire_fighting pipe network in each host fire_fighting pipe network, until the host extinguishing pipe
Net hydraulic pressure into the pipeline of the peripheral fire_fighting pipe network is consistent with hydraulic pressure in the host fire_fighting pipe network.
4. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as described in any one of claims 1-3, special
Sign is: the preparation stage step further includes will be multiple described on the host fire_fighting pipe network to the peripheral fire_fighting pipe network
Exhaust pipe is separately connected power station compression gas pipe.
5. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as described in any one of claims 1-3, special
Sign is: further comprising the steps of: after the preparation stage
Emergency response: fire brigade original place is guarded, and special messenger is allowed to carry out live inspection, until the step that fulfils assignment;
Described fulfil assignment after step further includes that notice fire brigade drops one's guard step.
6. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as claimed in claim 5, it is characterised in that: institute
Fire-fighting warning is further comprised the steps of: before stating emergency response step: notice fire brigade guards.
7. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as claimed in claim 5, it is characterised in that: institute
It is further comprised the steps of: before stating emergency response step
Operation warning: forbid each Steam Turbine system corresponding region and peripheral auxiliary system corresponding region fire operation;
It further include releasing to forbid each Steam Turbine system corresponding region and peripheral auxiliary system pair after the step that fulfils assignment
The step of answering region fire operation.
8. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as described in any one of claims 1-3, special
Sign is: the preparation stage step further include: protects in the interim pipeline of the master and the external extinguishing pipe junction setting
Column, and protective fence is set in the interim pipeline of the master and the external fire-fighting head junction.
9. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as claimed in claim 8, it is characterised in that: institute
State the step that fulfils assignment further include: further include the steps that removing the protective fence before removing the interim pipeline of master.
10. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as described in any one of claims 1-3, special
Sign is: the preparation stage step further include: setting is for being discharged the temporary drainage pump of water in draining melt pit;
The step that fulfils assignment further include: remove the temporary drainage pump.
11. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as claimed in claim 10, it is characterised in that:
The temporary drainage pump is set to the corresponding region of pipeline on the host fire_fighting pipe network to the peripheral fire_fighting pipe network.
12. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as claimed in claim 11, it is characterised in that:
Temporary drainage pump is set to the corresponding position of each drainpipe on the host fire_fighting pipe network to the peripheral fire_fighting pipe network.
13. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as described in any one of claims 1-3, special
Sign is: further comprising the steps of: before the preparation stage step
Time is selected: selecting a set of Steam Turbine and carries out large repairs.
14. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as claimed in claim 13, it is characterised in that:
It is further comprised the steps of: before the block isolation step
Overhaul is shut down: the Steam Turbine to overhaul being completed reactor core complete unloading operating condition, and by the corresponding main transformer of the Steam Turbine
Depressor is stopped transport.
15. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as claimed in claim 14, it is characterised in that:
It is further comprised the steps of: before the block isolation step, after Yu Suoshu overhaul outage
Evacuation procedure: oil, hydrogen in conventional island are emptied.
16. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as described in any one of claims 1-3, special
Sign is: the preparation stage step further includes transporting new valve at the corresponding isolating valve to be replaced.
17. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as claimed in claim 16, it is characterised in that:
The preparation stage step further includes the movable stand that setting supports each new valve respectively, and makes each method on each new valve
It is identical that the height and position of each flange hole is corresponded on flange aperture height and position and the isolating valve to be replaced.
18. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as described in any one of claims 1-3, special
Sign is: the preparation stage step further includes support frame being set up at each isolating valve to be replaced and each described to more
Rope is bound on the isolating valve changed, chain block is set on support frame as described above, by the chain suspension hook of the chain block
It is connected with the rope.
19. the synchronous method for replacing peripheral workshop fire-fighting water isolation valve of nuclear power station as claimed in claim 18, it is characterised in that:
The completion stage further includes removing each support frame as described above.
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Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2003270374A (en) * | 2002-03-19 | 2003-09-25 | Hitachi Ltd | Containment spray control device |
CN201741415U (en) * | 2010-07-30 | 2011-02-09 | 中广核工程有限公司 | Emergency water compensation device |
CN103165012A (en) * | 2011-12-14 | 2013-06-19 | 中国广东核电集团有限公司 | Training device and method of nuclear power station main steam isolating valve control system |
CN103778978A (en) * | 2012-10-25 | 2014-05-07 | 中国核动力研究设计院 | Integrated reactor main pump overhaul water draining and waste heat discharging method |
CN103915124A (en) * | 2013-10-18 | 2014-07-09 | 中广核核电运营有限公司 | Nuclear power station conventional island desalted water distribution system full-stop overhauling method |
CN204034106U (en) * | 2014-07-24 | 2014-12-24 | 广西防城港核电有限公司 | Nuclear power station fire water distribution system |
-
2019
- 2019-07-12 CN CN201910630502.5A patent/CN110448844B/en active Active
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2003270374A (en) * | 2002-03-19 | 2003-09-25 | Hitachi Ltd | Containment spray control device |
CN201741415U (en) * | 2010-07-30 | 2011-02-09 | 中广核工程有限公司 | Emergency water compensation device |
CN103165012A (en) * | 2011-12-14 | 2013-06-19 | 中国广东核电集团有限公司 | Training device and method of nuclear power station main steam isolating valve control system |
CN103778978A (en) * | 2012-10-25 | 2014-05-07 | 中国核动力研究设计院 | Integrated reactor main pump overhaul water draining and waste heat discharging method |
CN103915124A (en) * | 2013-10-18 | 2014-07-09 | 中广核核电运营有限公司 | Nuclear power station conventional island desalted water distribution system full-stop overhauling method |
CN204034106U (en) * | 2014-07-24 | 2014-12-24 | 广西防城港核电有限公司 | Nuclear power station fire water distribution system |
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