JPS6224757B2 - - Google Patents
Info
- Publication number
- JPS6224757B2 JPS6224757B2 JP53159266A JP15926678A JPS6224757B2 JP S6224757 B2 JPS6224757 B2 JP S6224757B2 JP 53159266 A JP53159266 A JP 53159266A JP 15926678 A JP15926678 A JP 15926678A JP S6224757 B2 JPS6224757 B2 JP S6224757B2
- Authority
- JP
- Japan
- Prior art keywords
- piping
- main steam
- water supply
- supply system
- water
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 56
- 238000012360 testing method Methods 0.000 claims description 30
- 238000004140 cleaning Methods 0.000 claims description 20
- 238000000034 method Methods 0.000 claims description 11
- 238000010276 construction Methods 0.000 description 11
- 238000002955 isolation Methods 0.000 description 7
- 238000002360 preparation method Methods 0.000 description 6
- 238000010586 diagram Methods 0.000 description 5
- 238000013461 design Methods 0.000 description 4
- 238000003466 welding Methods 0.000 description 4
- 238000012790 confirmation Methods 0.000 description 3
- 238000009430 construction management Methods 0.000 description 2
- 238000007796 conventional method Methods 0.000 description 2
- 238000004870 electrical engineering Methods 0.000 description 2
- 238000007689 inspection Methods 0.000 description 2
- 238000009434 installation Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- NJPPVKZQTLUDBO-UHFFFAOYSA-N novaluron Chemical compound C1=C(Cl)C(OC(F)(F)C(OC(F)(F)F)F)=CC=C1NC(=O)NC(=O)C1=C(F)C=CC=C1F NJPPVKZQTLUDBO-UHFFFAOYSA-N 0.000 description 2
- 238000010998 test method Methods 0.000 description 2
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical group [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 1
- 238000004378 air conditioning Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000003908 quality control method Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Cleaning In General (AREA)
Description
【発明の詳細な説明】
〔発明の目的〕
〔産業上の利用分野)
本発明は原子力発電所の建設に於ける主蒸気系
及び給水系配管水圧試験及び配管洗浄方法に関す
るものである。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] [Field of Industrial Application] The present invention relates to a method for hydraulic pressure testing and cleaning of main steam system and water supply system piping in the construction of a nuclear power plant.
(従来の技術)
以下、第1図及び第2図を参照して従来の原子
炉主蒸気系と給水系配管における配管水圧試験と
洗浄方法を説明する。(Prior Art) Hereinafter, a conventional piping hydraulic pressure test and cleaning method for the reactor main steam system and water supply system piping will be described with reference to FIGS. 1 and 2.
第1図において、原子炉格納容器9の周囲には
シールドウオール13が配置されている。この原
子炉格納容器9内には原子炉圧力容器8が収容さ
れており、この原子炉圧力容器8は原子炉圧力容
器ペデスタル(以下RPVペデスタルと略す)1
2によつて支持されている。前記原子炉圧力容器
9内で発生した主蒸気は主蒸気系配管1,14か
ら主蒸気隔離弁4、主蒸気第三隔離弁5を介して
タービン(図示せず)に導びかれる。このタービ
ンに導びかれた主蒸気は復水器(図示せず)にて
凝縮され復水となる。この復水は、給水系配管1
5,2から給水系隔離弁3を介して前記原子炉圧
力容器8内に導びかれる。そして、前記復水は再
循環系配管10から再循環系ポンプ11を介して
昇圧され、前記原子炉圧力容器8内を下方から上
方に向かつて流れ再び主蒸気と成つて前記主蒸気
系配管1に導びかれる様に成つている。ここで第
2図を参照して従来における主蒸気系配管及び給
水系配管の盲キヤツプによる水圧試験方法を示
す。 In FIG. 1, a shield wall 13 is arranged around the reactor containment vessel 9. As shown in FIG. A reactor pressure vessel 8 is housed in this reactor containment vessel 9, and this reactor pressure vessel 8 is a reactor pressure vessel pedestal (hereinafter abbreviated as RPV pedestal) 1.
Supported by 2. The main steam generated in the reactor pressure vessel 9 is guided from the main steam system pipes 1 and 14 to a turbine (not shown) via a main steam isolation valve 4 and a third main steam isolation valve 5. The main steam led to the turbine is condensed in a condenser (not shown) and becomes condensed water. This condensate is transferred to water supply system piping 1
5, 2, and is led into the reactor pressure vessel 8 via the water supply system isolation valve 3. Then, the condensate is pressurized from the recirculation system piping 10 via the recirculation system pump 11, flows from the bottom to the top inside the reactor pressure vessel 8, becomes main steam again, and is converted into the main steam system piping 1. It is designed to be guided by. Here, referring to FIG. 2, a conventional hydraulic pressure test method using blind caps for main steam system piping and water supply system piping will be described.
第2図において、従来工法によると、各々の主
蒸気系配管1,14、給水系配管2,15の施工
が進み、原子炉圧力容器8のノズル附近迄完成し
た時点で規定圧力に耐え得る様準備された盲キヤ
ツプ6を取付ける。数量は主蒸気系配管1に4
ケ、給水系配管2に6ケの計10ケの盲キヤツプ6
を取付ける。給水系配管2はこの時点で水圧試験
が可能となるが主蒸気系配管14は、隔離弁4を
止める為特殊治具17を取付けた後に水圧試験が
可能となる。これらの準備が完成した後水圧試験
を実施する。水圧試験は溶接検査耐圧試験及び使
用前耐圧試験の2回が官庁立会の対象となり、主
蒸気系、給水系の立合は4回受検する事になる。
この準備として、社内、客先各々最低2回実施す
る為、この2系統(主蒸気系、給水系)のみでも
8回の水圧試験が行なわれる。この水圧試験の都
度、日本電気協会電気技術規程に規定されている
最低使用温度の確認の為、配管の温度を規定温度
に上げなければならない。その為ハウスボイラー
蒸気を注入するのであるが循環方法を適切に行な
わないと検査不可となる。この様にして水圧試験
が終了すると次のステツプである配管洗浄の準備
にとりかかる。すなわち、配管の洗浄は水又は水
に薬品を溶かした溶液を配管内に注入し、洗浄対
象配管で循環ループを作り溶液を循環させて配管
を洗浄するものである。この洗浄時においては配
管の圧力を考える必要はなく、洗浄ルートのみの
仮配管をして洗浄作業を行なつていた。 In Fig. 2, according to the conventional construction method, the construction of the main steam system piping 1, 14 and the water supply system piping 2, 15 progresses, and when the area near the nozzle of the reactor pressure vessel 8 is completed, it will be possible to withstand the specified pressure. Attach the prepared blind cap 6. Quantity: 1 to 4 main steam system piping
ke, 6 blind caps 6 for water supply system piping 2, total 10 caps 6
Install. The water supply system piping 2 can be tested for water pressure at this point, but the main steam system piping 14 can be tested for water pressure after a special jig 17 is installed to stop the isolation valve 4. After these preparations are completed, a hydraulic test will be carried out. Two water pressure tests, the welding inspection pressure test and the pre-use pressure test, will be witnessed by government agencies, and the main steam system and water supply system will be witnessed four times.
In preparation for this, water pressure tests are conducted at least twice each in-house and at the customer's site, so eight hydraulic pressure tests are conducted on just these two systems (main steam system and water supply system). Each time this water pressure test is conducted, the temperature of the piping must be raised to the specified temperature in order to confirm the minimum operating temperature stipulated in the Electrical Technology Regulations of the Japan Electric Association. For this purpose, house boiler steam is injected, but inspections will not be possible unless proper circulation methods are used. Once the water pressure test is completed in this way, preparations for the next step, pipe cleaning, begin. That is, cleaning the piping involves injecting water or a solution of chemicals in water into the piping, creating a circulation loop around the piping to be cleaned, and circulating the solution to clean the piping. During this cleaning, there was no need to consider the pressure of the piping, and the cleaning work was performed by temporarily installing piping for only the cleaning route.
(発明の解決しようとする問題点)
以上の構成において、従来の配管水圧試験及び
洗浄方法は次の様な問題点があつた。(Problems to be Solved by the Invention) With the above configuration, the conventional piping water pressure testing and cleaning methods have the following problems.
第1に、第1図に示される如く格納容器内の配
管の位置的問題がある。即ち、狭い格納容器内に
機器、配管、サポートダクト、電気用コンジツト
ケーブル、計装配管が設置され且つ、工事が施工
されるので本配管の耐圧試験及び洗浄の時期は原
子力発電所建設の最盛期にあたり、同時作業のく
り返しは建設管理、安全管理、品質管理上の問題
があり困難度が大きい。また、第2として配管水
圧試験の条件である温度を上げる事がむずかし
い。即ち日本電気協会電気技術規程に規定されて
いる最低使用温度の確認の為、配管の温度を規定
温度に上昇させるのであるが配管の径が太く(主
蒸気系は24インチ、給水系20インチ)、この配管
の温度を上げるために配管にボイラー蒸気を通し
て温度を上げるのであるが、上述した従来の方法
によると本配管より別れた枝管からボイラー蒸気
を入れ循環時間に10時間以上要していた。又配管
径が大きく配管径路が長い為規定の温度確保がむ
ずかしく、配管水圧回数も社内確認、ユーザー確
認、官庁確認の最低3回を要し、これに要する準
備用具、準備要員等を加味すると延べ数千工数に
も達し、プラント建設ににおいてこの改善が必須
条件となつている。第3には、上述した従来工法
であると大口径の配管に取付けられる盲キヤツプ
の製作、取付に厳密な設計を要し据付管理にも充
分な注意を必要とし、(本管を傷つける)且つ配
管水圧、洗浄完了後の復旧作業においても同様な
注意が必要である。 First, as shown in FIG. 1, there is a problem with the position of the piping within the containment vessel. In other words, since equipment, piping, support ducts, electrical conduit cables, and instrumentation piping will be installed and construction work within the narrow containment vessel, pressure testing and cleaning of the main piping will take place during the peak of nuclear power plant construction. Due to the current period, repeated simultaneous work poses problems in construction management, safety management, and quality control, making it extremely difficult. Secondly, it is difficult to raise the temperature, which is a condition for piping water pressure testing. In other words, in order to confirm the minimum operating temperature stipulated in the Electrical Engineering Regulations of the Japan Electric Association, the temperature of the piping is raised to the specified temperature, but the diameter of the piping is large (24 inches for the main steam system and 20 inches for the water supply system). In order to raise the temperature of this pipe, boiler steam is passed through the pipe to raise the temperature, but according to the conventional method described above, boiler steam is introduced from a branch pipe separated from the main pipe and the circulation time takes more than 10 hours. . In addition, because the pipe diameter is large and the pipe route is long, it is difficult to maintain the specified temperature, and the number of pipe water pressure checks required at least three times: in-house confirmation, user confirmation, and government office confirmation.If you take into account the preparation tools and personnel required for this, the total number of This improvement has reached 1,000 man-hours and is an essential condition for plant construction. Third, the conventional method described above requires strict design for manufacturing and installing blind caps that are attached to large-diameter pipes, and requires sufficient care in installation management (damaging the main pipe). Similar precautions are required for pipe water pressure and restoration work after cleaning is completed.
第4に前述の水圧試験回数の関係から、所要日
数時間を多く必要とし、発電所建設のクリチカル
パスとなつている圧力容器ノズルへの最終継ぎ溶
接の時間がなくなり建設混乱を招く可能性があつ
た。 Fourth, due to the number of water pressure tests mentioned above, the required number of days and hours will increase, and there will be no time for final seam welding to the pressure vessel nozzle, which is a critical path in power plant construction, which may lead to construction confusion. Ta.
本発明は、上記の様な問題点を取り除き、作業
手順の簡略化、品質の向上、施工管理の向上を考
慮し且つ配管水圧・配管洗浄を行なう為決められ
た仕様を満足させ施工する方法を提供することを
目的とする。 The present invention eliminates the above-mentioned problems, takes into account the simplification of work procedures, the improvement of quality, and the improvement of construction management, and provides a construction method that satisfies the specified specifications for pipe water pressure and pipe cleaning. The purpose is to provide.
(問題点を解決するための手段)
本発明の特徴は給水系及び主蒸気系の配管の盲
キヤツプの代用として配管水圧試験・配管洗浄を
行なう為に満足させるべく仕様にて製作した配管
治具を給水系及び主蒸気系の配管に各々溶接接続
して行なう方法である。この配管治具の製作に当
つては本配管に要求されるべく耐圧(水圧)にも
つ様な配管肉厚を満足させるのは勿論の事、格納
容器内の狭い所で施工する為あらかじめ設計者に
より設計されこの指示に基づいて施工されるもの
である。
(Means for Solving the Problems) A feature of the present invention is a piping jig manufactured to meet specifications for performing piping water pressure tests and piping cleaning as a substitute for blind caps on piping for water supply systems and main steam systems. This is a method in which the pipes are welded to the water supply system and main steam system piping. When manufacturing this piping jig, it goes without saying that it must satisfy the pipe wall thickness to withstand pressure (water pressure) as required for this piping, and since it will be constructed in a narrow space inside the containment vessel, the designer The project will be designed and constructed based on these instructions.
(実施例)
以下、本発明の一実施例を第3図を用いて説明
する。なお、第3図において、第1図及び第2図
と同一部分には同一符号を付しその部分の構成の
説明は省略する。第3図に示す如くあらかじめ設
計者により設計された配管図及び配管治具取付図
により配管水圧試験又は配管洗浄の約1ケ月前よ
り製作用意された配管治具の取付作業を行なう。
この場合、格納容器9内の作業であり、主蒸気系
及び給水系の配管が1種配管であり、非常に重要
配管である事から母管への接続等に施工上の細心
の注意を要すると同時に安全上の注意が必要であ
る。原子炉格納容器9内には、前記の通り各種配
管、サポート、鉄構造物、空調ダクト、電気コン
デツト等が配置されている為、非常に狭い所とな
つている。ここに配置される主蒸気系配管14及
び給水系配管15の詳細ルート設計が固まると、
これを基として配管治具20の設計が開始され
る。これは主蒸気系、給水系配管設計に合せて水
圧試験の圧力に耐える肉厚を考え材料手配をし製
作していく。この完成時期は主蒸気系及び給水系
の完成1カ月前を設定する。即ち配管水圧試験の
1ケ月前に準備し完成前の主蒸気系配管1,14
及び給水系配管2,15を用意された配管治具2
0により接続し配管水圧試験、配管洗浄の準備を
完成させる。準備完了に伴い配管水圧試験となる
のであるが各々給水系配管15より主蒸気系配管
18にポンプ(図示せず)で水を送り、満水とし
他に用意されたコンプレツサー(図示せず)によ
り圧力を加え受検するのである。尚、配管条件試
験における温度を上げる作業(電気技術規程
JEAL―4206)であるがこれは給水系配管15と
主蒸気系配管14が配管治具20により接続され
ているのでボイラー蒸気を循環させる事により容
易に規定温度に上げる事が出来る。水圧試験の回
数は従来例と変化はないが水圧試験準備等で大幅
に改善させることができる。水圧試験完了後に配
管洗浄の工程が続くわけであるがそのままの循環
ルートを使つて洗浄を施工出来るのである。これ
が完了してから配管治具を取外し圧力容器への最
終溶接が実施される。(Example) An example of the present invention will be described below with reference to FIG. In FIG. 3, the same parts as in FIGS. 1 and 2 are designated by the same reference numerals, and the explanation of the structure of the parts will be omitted. As shown in FIG. 3, the piping jig is installed using the piping diagram and piping jig installation diagram that have been designed by the designer in advance about one month before the piping water pressure test or piping cleaning.
In this case, the work is inside the containment vessel 9, and the piping for the main steam system and water supply system is Class 1 piping, and as it is extremely important piping, great care must be taken in construction when connecting it to the main pipe, etc. At the same time, safety precautions are necessary. As described above, the reactor containment vessel 9 is a very narrow space because various piping, supports, iron structures, air conditioning ducts, electrical conduits, etc. are arranged inside the reactor containment vessel 9. Once the detailed route design of the main steam system piping 14 and water supply system piping 15 to be placed here is finalized,
Based on this, the design of the piping jig 20 is started. This will be manufactured by arranging materials and considering the wall thickness to withstand the pressure of the water pressure test, in accordance with the main steam system and water supply system piping design. The completion date is set to be one month before the completion of the main steam system and water supply system. In other words, the main steam system piping 1, 14 was prepared one month before the piping water pressure test and was not yet completed.
and a piping jig 2 prepared with water supply system piping 2, 15
0 to complete the pipe water pressure test and pipe cleaning preparations. Once the preparations are complete, a water pressure test will be carried out on the piping. Water is sent from the water supply system piping 15 to the main steam system piping 18 using a pump (not shown), and the water is filled with water, and the pressure is increased using a compressor (not shown) prepared elsewhere. In addition, take the test. In addition, work to raise the temperature in piping condition tests (Electrical Engineering Regulations)
JEAL-4206), in which the water supply system piping 15 and the main steam system piping 14 are connected by a piping jig 20, so that the boiler steam can be easily raised to a specified temperature by circulating it. The number of water pressure tests is the same as in the conventional example, but it can be significantly improved by preparing for the water pressure test. The pipe cleaning process continues after the water pressure test is completed, but cleaning can be carried out using the same circulation route. After this is completed, the piping jig is removed and final welding to the pressure vessel is performed.
以上説明したように、本発明方法によれば現在
原子力発電プラント建設に於けるクリチカルパス
になつている前記配管水圧試験から配管洗浄、そ
して圧力容器への最終配管溶接作業工程を大幅に
短縮させることができる。
As explained above, according to the method of the present invention, it is possible to significantly shorten the process of pipe hydraulic pressure testing, pipe cleaning, and final pipe welding to the pressure vessel, which are currently critical paths in nuclear power plant construction. I can do it.
第1図は原子力発電所に於ける原子炉格納容器
内の主蒸気系配管及び給水系配管を示す原子炉格
納容器の側面図、第2図は原子力発電所における
配管の水圧試験方法を示す概略系統図、第3図は
本発明の一実施例に係る原子力発電所の配管試
験・洗浄方法を示す概略系統図である。
1,14…主蒸気系配管、2,15…給水系配
管、3…給水系隔離弁、4…主蒸気隔離弁、5…
主蒸気第3隔離弁、8…原子炉圧力容器、9…原
子炉格納容器、20…配管治具。
Figure 1 is a side view of the reactor containment vessel showing the main steam system piping and water supply system piping inside the reactor containment vessel in a nuclear power plant, and Figure 2 is a schematic diagram showing the water pressure test method for piping in a nuclear power plant. System diagram, FIG. 3 is a schematic system diagram showing a method for testing and cleaning piping in a nuclear power plant according to an embodiment of the present invention. 1, 14... Main steam system piping, 2, 15... Water supply system piping, 3... Water supply system isolation valve, 4... Main steam isolation valve, 5...
Main steam third isolation valve, 8...Reactor pressure vessel, 9...Reactor containment vessel, 20...Piping jig.
Claims (1)
と給水系配管を所定の水圧試験圧力に耐えるよう
接続し前記主蒸気系及び給水系配管の水圧試験及
び洗浄作業を同時に順次行なうことを特徴とする
原子力発電所の配管試験・洗浄方法。1. Main steam system piping and water supply system piping located in a nuclear power plant are connected to withstand a predetermined water pressure test pressure, and the water pressure test and cleaning work of the main steam system and water supply system piping are performed simultaneously and sequentially. Nuclear power plant piping testing and cleaning methods.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP15926678A JPS5587095A (en) | 1978-12-26 | 1978-12-26 | Atomic power plant pipe test cleaning method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP15926678A JPS5587095A (en) | 1978-12-26 | 1978-12-26 | Atomic power plant pipe test cleaning method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5587095A JPS5587095A (en) | 1980-07-01 |
| JPS6224757B2 true JPS6224757B2 (en) | 1987-05-29 |
Family
ID=15690005
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP15926678A Granted JPS5587095A (en) | 1978-12-26 | 1978-12-26 | Atomic power plant pipe test cleaning method |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5587095A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP6773463B2 (en) * | 2016-06-20 | 2020-10-21 | 株式会社東芝 | Chemical decontamination method for pressurized water nuclear power plant |
-
1978
- 1978-12-26 JP JP15926678A patent/JPS5587095A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5587095A (en) | 1980-07-01 |
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