East Japan Earthquake on March 11, 2011 and Fukushima Dai-ichi Nuclear Power Station
|
|
- Vincent Patrick
- 6 years ago
- Views:
Transcription
1 East Japan Earthquake on March 11, 2011 and Fukushima Dai-ichi Nuclear Power Station August 13, 2012 Takeyuki INAGAKI Nuclear Seismic Engineering Centre Tokyo Electric Power Company All Rights Reserved 2011The Tokyo Electric Power Company, Inc.
2 The Great East Japan Earthquake [Date/Time] 2:46 pm on Fri, March 11, 2011 [Epicenter] Offshore Sanriku Coast (approx. 180 km from Fukushima NPSs) [Seismic Energy] Moment Magnitude (Mw) 9.0 Largest earthquake/tsunami in recorded history of Japan. [Dead/Missing] Approx. 20,000 All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 1
3 Observed Seismic Data Comparison between Basic Earthquake Ground Motion and the record of intensity Observation Point (The lowest basement of reactor buildings) Horizontal (N-S) Observed data (*interim) Maximum Response Acceleration (gal) Horizontal (E-W) Vertical Maximum Response Acceleration against Basic Earthquake Ground Motion (Gal) Horizontal (N-S) Horizontal (E-W) Vertical Unit *2 447 * Unit *2 550 *2 302 * Fukushima Daiichi Unit *2 507 *2 231 * Unit *2 319 *2 200 * Unit *2 548 *2 256 * Unit *2 444 * Unit * Fukushima Daini Unit *2 232 * Unit *2 216 *2 208 * Unit *2 205 *2 288 * *1: The above data are preliminary and may be subject to change. *2: The recording finished after about seconds All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 2
4 Damages caused by the Earthquake All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 3
5 Status and Actions after the Earthquake (1) The inside of the administration building was seriously damaged. People in the building were assembled at the parking lot to confirm if there were any casualties or injured persons. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 4
6 Status and Actions after the Earthquake (2) Emergency Response Team members moved to the seismic isolation building (Emergency Response Room) and confirmed: All the control rods of Unit 1-3 were automatically inserted into the core. The off-site power was lost and all the available EDGs were in operation. The RPV water level of Unit 1-3 was controlled by the isolation condenser (Unit 1) or the RCIC system (Unit 2 & 3). All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 5
7 Tsunami Observed at 1F 1 2 Breakwater (height: approx. 10m) 3 4 All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 6
8 Tsunami Observed at 1F 重油タンク Tank (height:5.5m) 撮影日 :2011/3/11 15:42 撮影日 :2011/3/11 15:42 撮影日 :2011/3/11 15:43 Date/time: 2011/3/11 15:42 Date/time: 2011/3/11 15:42 Date/time: 2011/3/11 15:43 Date/time: 撮影日 :2011/3/11 15:43 15:43 Date/time: 撮影日 :2011/3/11 15:43 15:43 Date/time: 撮影日 :2011/3/11 15:44 15:44 All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 7
9 Impact of Earthquake/Tsunami at Fukushima Daiichi NPS (1F) Observed seismic acceleration exceeded the design-basis in only limited locations. No damage to safety-related equipment due to the earthquake confirmed to date. Tsunami severely flooded most of the major buildings. Estimated tsunami height of approx. 13 m (43 ft) was much greater than the design-basis of 6.1 m (20 ft). Almost the entire area was flooded 1F Unit 6 Unit 5 Unit 1 Unit 2 Unit 3 Unit 4 Radwaste Processing building All Rights Reserved 2011The Tokyo Electric Power Company, Inc. (C)GeoEye 8
10 Impact of Earthquake/Tsunami at Fukushima Daini NPS (2F) Observed seismic acceleration was smaller than design-basis. Damage due to tsunami was less extreme compared to 1F. Estimated tsunami height of approx. 9 m was much greater than the design-basis of 5.2 m. Limited area was flooded 2F Unit 4 Unit 3 Unit 2 Unit 1 Ran up intensively Radwaste Processing building (C)GeoEye All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 9
11 Inundation Depths at 1F and 2F 1F Inundation Depth 2F Damage from the tsunami was much more severe at 1F compared to 2F. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 10
12 Damages caused by the Tsunami (1) All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 11
13 Damages caused by the Tsunami (2) The heavy-oil tank was carried to inland A large crane fell down here All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 12
14 Damages caused by the Tsunami (3) Heavy oil tank carried by the tsunami Crane carried and fell down by the tsunami All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 13
15 Damages caused by the Tsunami (4) 1 2 1Large amount of sea water came even to the place behind the reactor buildings 2Sand and silt carried by the tsunami All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 14
16 Damages caused by the Tsunami (5) The breakwater was destroyed All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 15
17 Damages caused by the Tsunami (6) All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 16
18 Damages caused by the Tsunami (7) All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 17
19 Status of Unit 1-3 immediately after the tsunami (1) Fallen into the Station Black Out (SBO): All safety and non-safety systems driven by electricity were not available. No lights in the control rooms, R/Bs, T/Bs, etc. No important instrumentations for Unit 1 &2 due to loss of AC power sources and DC 125V batteries; the reactor water level/ pressure, drywell pressure, wet-well (S/C) pressure, etc. ; Totally blind! The instrumentation of Unit 3 was available immediately after the tsunami but only lasted for about 30hours because the DC 125V battery charger was flooded. No communication media between the Emergency Response Room (ERR) and workers at the field: only two wired telephones available between the ERR and each control room. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 18
20 Status of Unit 1-3 immediately after the tsunami (2) The sea water systems were totally destroyed: no ultimate heat sink. Status of cooling and flooding of the reactors were as follows: Operation of the isolation condenser of Unit 1 was unclear. The RCIC system of Unit 3 tripped after about 21hours since the tsunami. Then the HPCI system was activated but worked only for about 14 hours. The RCIC system of Unit 2 worked for about three days after the tsunami but the actual status could not be confirmed at the control room. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 19
21 Integrity of Power Supply System After the Tsunami at 1F and 2F Power panel Unit 1 Unit 2 Can/ can not be used Power panel Can/c an not be used Power panel Fukushima Daiichi Unit 3 Unit 4 Unit 5 Unit 6 Can/can not be used Power panel Can/c an not be used Power panel Can/c an not be used Power panel Can/can not be used Fukushima Daini Unit 1 Unit 2 Unit 3 Unit 4 Power panel Can/c an not b e used Power panel Can/c an not b e used Power panel Can/ca n not be use d Power panel Can/ca n not be use d M/C P/C Emergency DG DC power supply Emergency use Regular use Emergency use Regular use 125V DC DG 1A DG 2A DG 3A DG 4A DG 5A(*2) DG 6A (*2) DG 1A DG 2A (*2) DG 3A (*2) DG 4A (*2) DG 1B DG 2B (air-cooled) (*1) DG 3B DG 4B (air-cooled) (*1) DG 5B(*2) DG 6B (air-cooled) DG 1B DG 2B (*2) DG 3B DG 4B (*2) HPCS DG (*2) DG 1H DG 2H (*2) DG 3H DG 4H M/C 1C M/C 2C M/C 3C M/C 4C M/C 5C M/C 6C M/C 1C M/C 2C M/C 3C M/C 4C M/C 1D M/C 2D M/C 3D M/C 4D M/C 5D M/C 6D M/C 1D M/C 2D M/C 3D M/C 4D - - M/C 2E - - M/C 4E - - HPCS DG M/C M/C 1H M/C 2H M/C 3H M/C 4H M/C 1A M/C 1B M/C 2A M/C 2B M/C 3A M/C 3B M/C 4A M/C 4B M/C 5A M/C 5B M/C 6A-1 M/C 6B-1 M/C 1A-1 M/C 1B-1 M/C 2A-1 M/C 2B-1 M/C 3A-1 M/C 3B-1 M/C 4A-1 M/C 4B-1 M/C 6A-2 M/C 6B-2 M/C 1A-2 M/C 1B-2 M/C 2A-2 M/C 2B-2 M/C 3A-2 M/C 3B-2 M/C 4A-2 M/C 4B-2 M/C 1S M/C 5SA-1 M/C 1SA-1 M/C 3SA-1 M/C 2SA M/C 3SA M/C 5SA-2 M/C 1SA-2 M/C 3SA M/C 5SB-1 M/C 1SB-1 M/C 3SB-1 M/C 2SB M/C 3SB M/C 5SB-2 M/C 1SB-2 M/C 3SB-2 - P/C 1C P/C 2C P/C 3C P/C 4C P/C 5C P/C 6C P/C 1C-1 P/C 2C-1 P/C 3C-1 P/C 4C-1 P/C 1D P/C 2D P/C 3D P/C 4D P/C 5D P/C 6D P/C 1C-2 P/C 2C-2 P/C 3C-2 P/C 4C P/C 2E - - P/C 4E - - P/C 6E P/C 1D-1 P/C 2D-1 P/C 3D-1 P/C 4D-1 P/C 1A P/C 2A P/C 3A P/C 4A P/C 5A P/C 6A-1 P/C 1D-2 P/C 2D-2 P/C 3D-2 P/C 4D-2 P/C 2A P/C 5A-1 P/C 6A-2 P/C 1A-1 P/C 2A-1 P/C 3A-1 P/C 4A-1 P/C 1B P/C 2B P/C 3B P/C 4B P/C 5B P/C 6B-1 P/C 1A-2 P/C 2A-2 P/C 3A-2 P/C 4A P/C 5B-1 P/C 6B-2 P/C 1B-1 P/C 2B-1 P/C 3B-1 P/C 4B-1 P/C 1S - - P/C 3SA - - P/C 5SA - - P/C 1B-2 P/C 2B-2 P/C 3B-2 P/C 4B P/C 5SA P/C 1SA P/C 3SA P/C 2SB P/C 3SB - - P/C 5SB - - P/C 1SB P/C 3SB - DC125V main DC125V P/C DC125V main DC125V main DC125V P/C DC125V DIST DC125V main DC125V main DC125V main DC125V main bus panel A 2A bus panel 3A bus panel 4A 5A CENTER 6A bus panel A bus panel A bus panel A bus panel A DC125V main DC125V P/C DC125V main DC125V main DC125V P/C DC125V DIST DC125V main DC125V main DC125V main DC125V main bus panel B 2B bus panel 3B bus panel 4B 5B CENTER 6B bus panel B bus panel B bus panel B bus panel B Sea water system A RHRS A RHRS A RHRS A RHRS A RHRS A RHRS A RHRS A RHRS A RHRS A SW B RHRS B RHRS B RHRS B RHRS B RHRS B RHRS B RHRS B RHRS B RHRS B O: operable X: damaged *1 functionality lost due to inundation of power panels *2 functionality lost due to the damage of sea water system All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 20
22 1F Unit 1 Schematic System Diagram (Status After Tsunami ) Stack D/W vent valve IC SRV Tb Gen RPV Condenser CWP S/C vent valve SLC CRD RFP H/W CP Sea :Operable :Inoperative due to power loss : Briefly Operative CS CCS from CST & H/W HPCI MUWC CST CCSW Sea D/G DD FP Filtrated Water Tank All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 21 Sea
23 1F Unit 2 Schematic System Diagram (Status After Tsunami ) Stack D/W vent valve SRV Tb Gen RPV Condenser CWP S/C vent valve SL C CRD MD- RFP TD- RFP H/W HPCP LPCP Sea :Operable :Inoperative due to power loss :Inoperative CS RHR from CST & H/W RCIC HPCI CST RHRS Sea D/G MUWC DD FP Filtrated Water Tank All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 22 Sea
24 1F Unit 3 Schematic System Diagram (Status After Tsunami ) Stack D/W vent valve SRV Tb Gen RPV Condenser CWP S/C vent valve SL C CRD MD- RFP TD- RFP H/W HPCP LPCP Sea :Operable :Inoperative due to power loss :Inoperative CS RHRS Sea RH R from CST & H/W D/G RCIC HPCI MUWC DD FP CST Filtrated Water Tank All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 23 Sea
25 Actions taken for Unit 1-3 trying to avoid catastrophic conditions during the period since 11 th to 15 th March 2011 Establishing an alternative method to inject water into the reactor pressure vessel (RPV). Reduction of the RPV pressure using the SRVs. (Unit 2&3) Ventilation of the primary containment vessel (PCV). Recovery of the most important instrumentations: reactor water level rector pressure drywell pressure wet-well (suppression chamber: S/C) pressure. Recovery of the lights in the control rooms and other power supply sources. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 24
26 What were available for the recovery work after the tsunami? Only very limited devices and tools such as follows were available! Fire Engines: only a few people knew how to operate them. Flashlights Cable Tools (screwdrivers, etc.) Batteries taken from cars Engine driven Generators* Engine driven Air Compressors* *They were in the warehouses of the affiliated companies and difficult to find. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 25
27 Chronology of Unit 1 Scram response Deteriorating operability due to the tsunami Preparations for water injection Preparations for venting Water injection started Venting Prior to earthquake March 11, :46 March 11 17:12 Site superintendent directed consideration for injection of water into reactors using fire protection lines and vehicles March 12 5:46 Fire-fighting vehicle started injection of fresh water (water source: fire cistern) In rated power operation Great East Japan Earthquake occurred, reactor automatically scrammed [SHUTDOWN] 15:37 Station black out due to tsunami strike (Sea water systems also lost) Water injection Venting [COOLING] [CONTAINMENT] March 12 19:04 Injection of sea water started March 12 0:06 As D/W pressure might have exceeded 600kPa abs, site superintendent directed preparations for PCV venting 10:17 Containment vessel venting commenced 14:30 D/W pressure decreased. Containment vessel venting successful March 12 15:36 Explosion Occurred All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 26
28 Major Activities at 1F Unit 1 <factors disturbing recovery work (inside the building) > Scram response Due to lack of power sources, initial recovery activities had to be conducted in complete darkness, without any instrumentation, and without most communications means. Deteriorating operability due to the tsunami Many scattered objects were on the floor of the service building. Preparations for water injection Preparations for venting Water injection started Venting Connected temporary batteries to recover instrumentations. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 27
29 Major Activities at 1F Unit 1 <factors disturbing recovery work (inside the building) > Scram response Deteriorating operability due to the tsunami Instruments were monitored wearing a full face mask with a flashlight in complete darkness Check indicated values only with a flashlight in complete darkness. Preparations for water injection Preparations for venting Water injection started Venting Supervising at a deputy supervisor s desk wearing a full face mask in complete darkness. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 28
30 Major Activities at 1F Unit 1 <factors disturbing recovery work (outside the building) > Scram response Deteriorating operability due to the tsunami Many obstacles on access routes disturbed access to the field. Vehicles had to avoid passing over fire protection hoses laid in the field. Most of the prepared communication tools between the ERC and the control room were unavailable. Preparations for water injection Preparations for venting Water injection started Venting All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 29
31 Major Activities at 1F Unit 1 <Containment Vessel Venting Operation (1) > Scram response Deteriorating operability due to the tsunami Preparations for water injection Preparations for venting Water injection started Venting Two valves, a PCV vent valve (MO valve) and a S/C vent valve (AO valve: small) were selected as the target for manual PCV venting operation. Manual valve operation were planned to be conducted by 3 teams with 2 shift workers per team (one worker per team would be difficult due to the total darkness) and shift supervisors and vicesupervisors were selected to the team members. Equipment for the teams included fire-resistant clothing, self-contained breathing apparatus, APD, survey meter and flash light. At 9:03, it was confirmed that evacuation from the vicinity of south side of the NPS completed. At 9:04, the team members headed to the site for the venting operation. Cylinder MO MO 210 manually open valve Solenoid valve IA 電磁弁 AO AO 90 IA AO AO ボMO ンベラプチャーディスク Shift workers operation to AO AO 83 閉 Closed AO 1 AO 閉 Closed Closed Rupture disc Broke at 0.549MPa-abs 0.549MPabs で破壊 閉 Closed ボンベ閉 Cylinder Exhaust 排気筒 stack D/W maximum operating pressure: 0.528MPa-abs D/W 最高使用圧力 0.528MPabs Self-contained breathing apparatus 電磁弁 All Rights Reserved 2011The Tokyo Electric Power Company, Inc. Solenoid valve 30 RPV D/W Venting ベント実施圧力 pressure: 0.954MPabs 0.954MPa-abs
32 Major Activities at 1F Unit 1 <Containment Vessel Venting Operation (2) > Scram response Supply AC power to the solenoid valve of the AOVs using an engine generator Supply air to the AOVs using an engine compressor Deteriorating operability due to the tsunami Preparations for water injection Preparations for venting Water injection started Venting The AC power was lost: alternative supply from an engine-generator Engine driven Air Compressor for construction work Cylinder MO MO 210 Solenoid valve IA 電磁弁 AO AO 90 IA AO AO ボMO ンベ電磁弁 Solenoid valve ラプチャーディスク AO 83 AO AO 1 AO 閉 Closed Closed Rupture disc Broke at 0.549MPa-abs 0.549MPabs で破壊 閉 Closed 閉 Closed ボンベ閉 Cylinder Exhaust 排気筒 stack D/W maximum operating pressure: 0.528MPa-abs D/W 最高使用圧力 0.528MPabs RPV D/W Venting ベント実施圧力 pressure: 0.954MPabs 0.954MPa-abs All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 31
33 Testimonies from the Field (Operators) In an attempt to check the status of Unit 4 D/G, I was trapped inside the security gate compartment. Soon the tsunami came and I was a few minutes before drowning, when my colleague smash opened the window and saved my life. In total darkness, I could hear the unearthly sound of SRV dumping steam into the torus. I stepped on the torus to open the S/C spray valve, and my rubber boot melted. The radiation level in the main control room was increasing 0.01 msv (1 mrem) every 3 seconds but I couldn t leave I felt this was the end of my life. I asked for volunteers to manually open the vent valves. Young operators raised their hands as well; I was overwhelmed. Unit 3 could explode anytime soon, but it was my turn to go to the main control room. I called my dad and asked him to take good care of my wife and kids should I die. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 32
34 Testimonies from the Field (Maintenance Persons) We saw our car crashed by the explosion of the Unit 3. If we had gotten on the car a few minutes earlier, all of us would have been dead. We were replacing fire hoses when the explosion of Unit 3 occurred. We felt almost dying since many large rubbles were falling down to us. I urgently ran underneath a nearby fire engine. One of my colleagues got injuries in his leg and stomach. There were so many manholes opened by the tsunami. In order to lay cables, we had to proceed step by step carefully checking safety in the complete darkness. We were working in the Unit 3/4 control room when the explosion occurred. I was resigned to my fate. Dose rate was going up in the room after the explosion and we desperately tried to find places with lower dose rate. After replacing an air cylinder for the PCV ventilation of Unit 3, I heard sound of steam and saw white mist around us. I got into a panic for a while. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 33
35 Current Status and Roadmap Towards Restoration On Dec. 16, 2011, goals of Step 2 of Roadmap Towards Restoration was achieved. Reactors were determined to have achieved cold shutdown condition and that sufficiently low radiation dose at the site boundary can be maintained even if unexpected events were to occur. On Dec. 2nd, 2011, Interim Report on Fukushima Nuclear Accidents compiled by the TEPCO-Internal Investigation Committee was released. Consolidated facts regarding the accident, conducted root-cause analyses and identified action items to be implemented. Investigation of facts and identification of lessons learned will continue. Installation of Unit 1 R/B Cover All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 34
36 Current Status and Roadmap Towards Restoration (cont d) Accumulated Water Treatment Facilities All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 35
37 Current Status and Roadmap Towards Restoration (cont d) All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 36
38 Mid- to Long-Term Road Map Towards Decommissioning of 1F Units 1-4 Completion of Step 2 Within 2 years Within 10 years 30 to 40 years Phase-1 Phase-2 Phase-3 Period until commencement of fuel removal from the spent fuel pools Period until commencement of removal of fuel debris Period until completion of decommissioning Illustration of Fuel Debris Removal Process Global collaboration needed to work on unprecedented R&D undertaking. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 37
39 Analysis of Core Damage Condition of Fukushima Daiichi Units 1-3 Unit 1 PCV Units 2/3 PCV RPV RPV CS FDW CS FDW 2.6 m 2.6 m 7.6 m 7.6 m Fuels completely melted and relocated to the bottom of RPV. RPV breach likely occurred, leading to molten core-concrete interaction at the PCV pedestal floor. Max. penetration depth of 0.65 m. Fuels damaged but significant damage to the RPV leading to large amount of fuel dropping into the PCV floor unlikely. If damaged fuel had to dropped into the PCV floor, molten core-concrete interaction would have occurred. Max. penetration depth of 0.12 m (Unit 2) / 0.20 m (Unit 3). Core-Concrete Interaction stopped within the PCV steel plate and fuel is currently cooled. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 38
40 Summary (1) A large scale earthquake attacked the plant. According to the operation data, however, it can be concluded that plant behaviors before the tsunami was as designed, and up to now no damage due to the earthquake was found on safety-significant Systems, Structures and Components (SSCs). The height of the tsunami at Fukushima Dai-ichi was much higher than the plant design assumption and that observed at Fukushima Dai-ni. All electric power supply including DC 125V was lost for Unit 1-4 after the tsunami. For Unit 5&6, only one diesel generator, DG6B, was survived. After the tsunami, very limited tools and devices such as fire protection cars, batteries taken from cars and handy lights were available. In such circumstance, the Emergency Response Team members made their greatest efforts to avoid catastrophic conditions of Unit 1-3. Also for Unit 5&6, great efforts were made by the operators and maintenance people to make the units into a stable condition. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 39
41 Summary (2) Measures taken after the Niigata Chuetsu Oki Earthquake were certainly effective to ease the consequence of the accident: Seismic Isolation Building Self Fire Protection Team and Fire Engines Emergency Response Drills Up to now cooling systems for the reactors and spent fuel pools, and covering for the reactor building of Unit 1 have been established. Many projects are still being implemented. The plant staff members are dully cooperating with engineers of the stabilization centre and headquarters. From the plant point of view, it is very important to treat and manage contaminated water accumulated in the turbine buildings. Industrial safety of the recovery work is also very important. The plant staff members make a lot of efforts to improve work management and environment. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 40
42 Thank you very much for your attention. All Rights Reserved 2011The Tokyo Electric Power Company, Inc. 41
The nuclear reactor core of units 1 3 of Fukushima Daiichi NPS (1F1, 1F2, 1F3)
Responses taken to fight the nuclear accident and to mitigate the consequences Hisashi NINOKATA Professor, Politecnico di Milano Department of Energy CeSNEF-Nuclear Engineering Division Nuclear Reactors
More informationTEPCO s Safety Assurance Philosophy on Nuclear Power Generation Plants
TEPCO s Safety Assurance Philosophy on Nuclear Power Generation Plants January 25, 2013 Tokyo Electric Power Company, Inc. This English translation has been prepared with the intention of creating an accurate
More informationLeaks from Unit-3 PCV and steam release in a large amount
Attachment 3-8 Leaks from Unit-3 PCV and steam release in a large amount 1. Background At Unit-3 the suppression chamber (S/C) vent line configuration was completed at 08:41 on March 13 th and the dry
More informationNuclear safety Lecture 4. The accident of the TMI-2 (1979)
Nuclear safety Lecture 4. The accident of the TMI-2 (1979) Ildikó Boros BME NTI 27 February 2017 The China Syndrome Opening: 16 March 1979 Story: the operator of the Ventana NPP tries to hide the safety
More informationEvaluation of the fraction of Unit-3 vent gas that flowed into Unit-4 reactor building
Attachment 3-1 Evaluation of the fraction of Unit-3 vent gas that flowed into Unit-4 reactor building 1. Introduction The hydrogen explosion, which occurred on March 15, 211, at the Unit-4 reactor building
More informationTokyo Electric Power Company Holdings, Inc. November 30, 2017
< R e f e r e n c e > Partial damage to temperature gauge cables for the Reactor Pressure Vessel (RPV) found during the Fukushima Daiichi NPS Unit 3 Primary Containment Vessel () internal investigation
More informationUnit 2 Primary Containment Vessel Internal Investigation
Unit 2 Primary Containment Vessel Internal Investigation December 21, 2017 Tokyo Electric Power Company Holdings, Inc. 1. Conditions inside the Unit 2 Primary Containment Vessel According to accident development
More informationExtensive Damage Mitigation Guidelines (EDMG)
Extensive Damage Mitigation Guidelines (EDMG) Roy Harter RLH Global Services Regional Workshop on Sharing Best Practices in Development and Implementation of Severe Accident Management Guidelines October
More informationPower Supply Facilities Failure (Units 3-4 Temporary M/C (A), etc.) March 22, 2013 Tokyo Electric Power Company
< Reference > Power Supply Facilities Failure (Units 3-4 Temporary M/C (A), etc.) March 22, 2013 Tokyo Electric Power Company Occurrence of Events in a Chronological Order At around 6:57 PM on March 18,
More informationIEM on Severe Accident Management in the light of the accident at the Fukushima Daïchi NPP
IEM on Severe Accident Management in the light of the accident at the Fukushima Daïchi NPP Progress, challenges and perspectives in the field of design features, as regards SAMG IAEA, March 2014 Introduction
More informationACCIDENT MANAGEMENT AND EPR AT DUKOVANY NPP
ACCIDENT MANAGEMENT AND EPR AT DUKOVANY NPP 27-29 September 2017 Vienna IAEA Miroslav Trnka OVERVIEW General EOPs and SAMGs (changes) DAM (FLEX) EDMG Equipment (new + ongoing projects) Staff (drills and
More informationAccident Management Strategies for Mark I and Mark III BWRs
Accident Management Strategies for Mark I and Mark III BWRs E. L. Fuller Office of Nuclear Regulatory Research United States Nuclear Regulatory Commission IAEA Workshop Vienna, Austria July 17-21, 2017
More informationFUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER I: AUXILIARY SYSTEMS. A high-capacity EBA system [CSVS] [main purge]
PAGE : 1 / 9 5. CONTAINMENT PURGE (EBA [CSVS]) The Reactor Building purge system comprises the following: A high-capacity EBA system [CSVS] [main purge] A low-capacity EBA system [CSVS] [mini-purge] 5.1.
More informationDevelopment of a technology to investigate inside the Reactor Primary Containment Vessel (PCV)
Development of a technology to investigate inside the Reactor Primary Containment Vessel (PCV) - Results of follow up check after the site test - [For April 18 and 19, 2015] April 20, 2015
More informationCONTENTS OF THE PCSR CHAPTER 1 - INTRODUCTION AND GENERAL DESCRIPTION
PAGE : 1 / 8 CONTENTS OF THE PCSR CHAPTER 1 - INTRODUCTION AND GENERAL DESCRIPTION SUB-CHAPTER 1.1 INTRODUCTION SUB-CHAPTER 1.2 GENERAL DESCRIPTION OF THE UNIT SUB-CHAPTER 1.3 COMPARISON WITH REACTORS
More informationDynamic Context Quantification for Design Basis Accidents List Extension and Timely Severe Accident Management
Dynamic Context Quantification for Design Basis Accidents List Extension and Timely Severe Accident Management Emil Kostov a,b and Gueorgui Petkov a a Technical University, Sofia, Bulgaria b WorleyParsons,
More informationFUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER F: CONTAINMENT AND SAFEGUARD SYSTEMS 7. CONTAINMENT HEAT REMOVAL SYSTEM (EVU [CHRS])
PAGE : 1 / 16 7. CONTAINMENT HEAT REMOVAL SYSTEM (EVU [CHRS]) 7.0. SAFETY REQUIREMENTS 7.0.1. Safety functions The main functions of the EVU system [CHRS] are to limit the pressure inside the containment
More informationInstrumentation systems of BWR
Instrumentation systems of BWR 1 Reactor core and pressure vessel of BWR Fuel rod Fuel assembly Reactor vessel :15~22cm thickness of steel, height of 21m, diameter of 7m Steam dryer Pressure vessel Main
More informationDETAILS OF THE ACCIDENT PROGRESSION IN 1F1
DETAILS OF THE ACCIDENT PROGRESSION IN 1F1 EMUG 2019 BRAUN, Matthias Switzerland, 3 rd -5 th April 2019 Not part of the BSAF OECD Benchmark Project Relying exclusively on publically available input data
More informationAnalysis of the hydrogen explosion at the Unit-1 Reactor Building
Attachment 1-10 Analysis of the hydrogen explosion at the Unit-1 Reactor Building 1. Introduction A hydrogen explosion occurred on March 12 th, 2011 at the Unit-1 Reactor Building (hereafter the R/B in
More informationRecent Research on Hazards PSA
Recent Research on Hazards PSA Marina Röwekamp, Hartmut Holtschmidt, Michael Türschmann Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) ggmbh IEM8 - International Experts Meeting on Strengthening
More informationControl Performance: An Imperative for Safety
Control Performance: An Imperative for Safety George Buckbee 2014 ExperTune, a Metso Company Page 1 Control Performance: An Imperative for Safety George Buckbee, ExperTune 2014 ExperTune, a Metso Company
More informationIAEA Training in Level 2 PSA MODULE 8: Coupling Source Terms to Probabilistic Event Analysis (CET end-state binning)
IAEA Training in Level 2 PSA MODULE 8: Coupling Source Terms to Probabilistic Event Analysis (CET end-state binning) The Problem A probabilistic treatment of severe accident progression leads to numerous
More informationREGULATORY OBSERVATION
RO unique no.: REGULATORY OBSERVATION REGULATOR TO COMPLETE RO-ABWR-0046 Date sent: 20 th April 2015 Acknowledgement required by: 08 th May 2015 Agreement of Resolution Plan required by: 14 th May 2015
More informationCustom-Engineered Solutions for the Nuclear Power Industry from SOR
Custom-Engineered Solutions for the Nuclear Power Industry from SOR As the world s aging nuclear power plants continue to be challenged with maintenance and Instrumentation Solutions for the Nuclear Power
More informationUKEPR Issue 04
Title: PCSR Sub-chapter 6.8 Main steam relief train system - VDA [MSRT] Total number of pages: 16 Page No.: I / III Chapter Pilot: M. LACHAISE Name/Initials Date 25-06-2012 Approved for EDF by: A. PETIT
More informationThe Nitrogen Threat. The simple answer to a serious problem. 1. Why nitrogen is a risky threat to our reactors? 2. Current strategies to deal with it.
International Conference on Topical Issues in Nuclear Installation Safety: Safety Demonstration of Advanced Water Cooled Nuclear Power Plants. The simple answer to a serious problem Vienna. 6 9 June 2017
More informationIntegrated Coping Strategies for Beyond-Design-Basis External Events
IAEA IEM on SAM in the Light of the Fukushima Daiichi NPP, 17-20 March 2014, Vienna, Austria Integrated Coping Strategies for Beyond-Design-Basis External Events Jaewhan Kim and Kwang-Il Ahn KAERI Contents
More informationSafety and efficiency go hand in hand at MVM Paks NPP
International Forum Atomexpo 2018 Safety and efficiency go hand in hand at MVM Paks NPP József Elter MVM Paks Nuclear Power Plant Ltd. Hungary Start up Four of the VVER-440/V213 unit Power units up-rate
More informationBOILER MECHANIC//SR. BOILER MECHANIC
WORKING IN STEAM MANHOLES Activity Hazard Identification Required Precautions 1. Driving to and from work site. 1. Motor vehicle accident; striking pedestrians, bicyclists, or individuals using rollerblades.
More informationSYSTEM IDENTIFICATION AND RESPONSE ANALYSIS OF RC HIGH-RISE BUILDINGS UNDER SUCCESSIVE EARTHQUAKES
SYSTEM IDENTIFICATION AND RESPONSE ANALYSIS OF RC HIGH-RISE BUILDINGS UNDER SUCCESSIVE EARTHQUAKES Muhammad Rusli MEE54 Supervisor: Taiki SAITO ABSTRACT System identification was performed to two RC high-rise
More informationFukushima: Outside the Imagination and Lack of Preparation. Benefit of PST (Partial Stroke Test)
International TÜV Rheinland Symposium in China Functional Safety in Industrial Applications 18 19 October 2011, Shanghai - China Fukushima: Outside the Imagination and Lack of Preparation & Benefit of
More informationVerification and validation of computer codes Exercise
IAEA Safety Assessment Education and Training (SAET) Programme Joint ICTP- IAEA Essential Knowledge Workshop on Deterministic Safety Assessment and Engineering Aspects Important to Safety Verification
More informationThe latest automotive systems require innovative leak test methods and fixturing.
Leak Testing Auto Parts The latest automotive systems require innovative leak test methods and fixturing. In the past, automobile manufacturers only required basic forms of leak testing to check standard
More informationExperimental Verification of Integrated Pressure Suppression Systems in Fusion Reactors at In-Vessel Loss-of -Coolant Events
Experimental Verification of Integrated Pressure Suppression Systems in Fusion Reactors at In-Vessel Loss-of -Coolant Events K. Takase 1), H. Akimoto 1) 1) Japan Atomic Energy Research Institute (JAERI),
More informationThe Failure of the Kamaishi Tsunami Protection Breakwater
PT-13: Coastal and Ocean Engineering ENGI.8751 Undergraduate Student Forum Faculty of Engineering and Applied Science, Memorial University, St. John s, NL, Canada March, 2013 Paper Code. (PT-13 - Tucker)
More informationHow to reinforce the defence-indepth in NPP by taking into account natural hazards?
How to reinforce the defence-indepth in NPP by taking into account natural hazards? Caroline LAVARENNE Karine HERVIOU Patricia DUPUY Céline PICOT IAEA 21-24 October 2013, Vienna Introduction The DiD has
More informationAssessment of Internal Hazards
Joint ICTP- Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety Trieste, 12-23 October 2015 Assessment of Internal Hazards Javier Yllera Department
More informationConsiderations for the Practical Application of the Safety Requirements for Nuclear Power Plant Design
Considerations for the Practical Application of the Safety Requirements for Nuclear Power Plant Design Joint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects
More informationFUNDAMENTAL SAFETY OVERVIEW VOLUME 2: DESIGN AND SAFETY CHAPTER P: REFERENCE OPERATING CONDITION STUDIES (PCC)
PAGE : 1 / 11 1. PASSIVE SINGLE FAILURE ANALYSIS The aim of the accident analysis in Chapter P is to demonstrate that the safety objectives have been fully achieved, despite the most adverse single failure.
More informationPress Release / Briefing Paper 9 May 2014 Contact: Aileen Mioko Smith cell:
p 1 Press Release / Briefing Paper 9 May 2014 Contact: Aileen Mioko Smith cell: +81-90-3620-9251 email: amsmith@gol.com Will Japan Restart Nuclear Power Yet Again Ignoring Danger of Earthquakes? Osaka
More informationASVAD THE SIMPLE ANSWER TO A SERIOUS PROBLEM. Automatic Safety Valve for Accumulator Depressurization. (p.p.)
ASVAD Automatic Safety Valve for Accumulator Depressurization (p.p.) THE SIMPLE ANSWER TO A SERIOUS PROBLEM International Experts Meeting on Strengthening Research and Development Effectiveness in the
More informationSEVERE INJURY WITH HAND AMPUTATION AND SKULL FRACTURE
HSE Bulletin Page no.1 SEVERE INJURY WITH HAND AMPUTATION AND SKULL FRACTURE Type of accident: Data of accident: Job position: Type of activity: Activity performed: Lost Time Injury March, 14 th 2003 Motorman
More informationWIND SPEED LENGTH OF TIME WIND BLOWS (Duration) DISTANCE OVER WHICH IT BLOWS (Fetch)
WAVES Up and down movement of ocean surface Transportation of energy across the water over vast distances If not stopped by anything, waves can travel entire oceans Size and speed depend upon: WIND SPEED
More information1 SE/P-02. Experimental and Analytical Studies on Thermal-Hydraulic Performance of a Vacuum Vessel Pressure Suppression System in ITER
1 SE/P-2 Experimental and Analytical Studies on Thermal-Hydraulic Performance of a Vacuum Vessel Pressure Suppression System in ITER K. Takase 1), H. Akimoto 1) 1) Japan Atomic Energy Research Institute,
More informationOPERATING PROCEDURES
OPERATING PROCEDURES 1.0 Purpose This element identifies Petsec s Operating Procedures for its Safety and Environmental Management System (SEMS) Program; it applies to all Petsec operations. Petsec is
More informationHOT TOPIC REPORT OF BOTTOM HEADER DEFECTED,YGN PLANT 5 IN 2003 KOREA HYDRO AND NUCLEAR POWER COMPANY
HOT TOPIC REPORT OF BOTTOM HEADER DEFECTED,YGN PLANT 5 IN 2003 KOREA HYDRO AND NUCLEAR POWER COMPANY ꌙꌙꌙ Table of Contents ꌙꌙꌙ Ⅰ. General Description Ⅱ. The Concept of Rx Vessel and Position of
More information/ Air Line Kit AL - M1202. / OPERATION MANUAL P1 - P9 / English P11 - P19 OM-K0651
/ Air Line Kit AL - M1202 / OPERATION MANUAL P1 - P9 / English P11 - P19 OM-K0651 002 1 Thank you for purchasing the Air Line Kit " AL - M1202 ". This Air Line Kit is designed to adjust the air supply
More informationSAFETY MANAGEMENT SYSTEM
Equipment Location: Hazard Hired From All Master Hire Stores Entanglement Can anyone s hair, clothing, gloves, necktie, jewellery, cleaning brushes, rags or other materials become entangled with moving
More informationSAFETY MANAGEMENT SYSTEM
Equipment Location: Hazard Hired From All Master Hire Stores Entanglement Can anyone s hair, clothing, gloves, necktie, jewellery, cleaning brushes, rags or other materials become entangled with moving
More informationSAFETY MANAGEMENT SYSTEM
Equipment Location: Hazard Hired From All Master Hire Stores Entanglement Can anyone s hair, clothing, gloves, necktie, jewellery, cleaning brushes, rags or other materials become entangled with moving
More informationIAEA SAFETY STANDARDS for protecting people and the environment
IAEA SAFETY STANDARDS for protecting people and the environment DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS DRAFT SAFETY GUIDE DS 482 STATUS: STEP 11 Submission to Review
More informationERIC LAFFORGUE. The Atomic surfers from Fukushima
ERIC LAFFORGUE The Atomic surfers from Fukushima On 11 March 2011, at 2.46 pm, Japan was hit by a magnitude 9.0 earthquake which generated a tsunami on the coast. Here, on Futaba beach, the giant wave
More informationReview of the Hall B Gas System Hardware. George Jacobs
of the Hardware George Jacobs DSG Staff 2 Hall B Gas Utilities for detectors Drift Chamber (DC) Low Threshold Cherenkov Counter (LTCC) Micromegas Vertex Tracker (MVT) Forward Tagger (FT) Ring Imaging Cherenkov
More informationOcean Motion Notes. Chapter 13 & 14
Ocean Motion Notes Chapter 13 & 14 What is a Wave? Wave: movement of energy through a body of water How are Waves Caused? Caused mostly by wind Wind blowing on the water transmits energy to the water Size
More informationReclaim Basic Set Up
This purpose of the document is to simplify the set up and understand the Gas Services reclaim system functions. The Gas Services Reclaim Manual is to be used for reference, maintenance, and servicing.
More informationTemporary Increase in the Emergency Exposure Dose Limit in Response to the TEPCO Fukushima Daiichi NPP Accident December 3, 2014
ひと くらし みらいのために 厚生労働省 Temporary Increase in the Emergency Exposure Dose Limit in Response to the TEPCO Fukushima Daiichi NPP Accident December 3, 2014 Shojiro Yasui,, PhD Office for Radiation Protection
More informationSAFETY MANAGEMENT SYSTEM
Equipment Location: Hazard Hired From All Master Hire Stores Entanglement Can anyone s hair, clothing, gloves, necktie, jewellery, cleaning brushes, rags or other materials become entangled with moving
More informationNatural Gas Conditioning Skids & Equipments
Natural Gas Conditioning Skids & Equipments NATURAL GAS CONDITIONING SKIDS NIRMAL has rich experience of supplying complete package of Natural Gas conditioning skids consisting of emergency shut down,
More informationPipeline Integrity Valve Spacing Engineering Assessment (CDN) Grande Prairie Mainline Loop 2 (Progress Section) NPS 36
APPROVALS Library: EDMS General Page 1 of 10 TABLE OF CONTENTS APPROVALS 1 1. PURPOSE... 3 2. BACKGROUND... 3 3. VALVE SPACING ASSESSMENT APPROACH... 6 4. OPERATIONS AND MAINTENANCE CONSIDERATIONS... 6
More informationSECTION 2 APPLICATION OF FUNDAMENTALS
SECTION 2 APPLICATION FUNDAMENTALS ENVIRONMENTAL CONDITIONS IN NEC CLASS I HAZARDOUS LOCATIONS Section II covers a great number of illustrations which can be applied directly to a hazardous area under
More informationMAINTENANCE MECHANIC RCF
WORKING ON ATC EQUIPMENT MAINTENANCE MECHANIC Activity Hazard Identification Required Precautions 1. Driving to and from work site. 1. Motor vehicle accident; striking pedestrians, bicyclists, or individuals
More informationPeriodic Survey of Fuel Installations on Ships other than Liquefied Gas Carriers utilizing gas or other low flash point fuels
(Jan 2017) Periodic Survey of Fuel Installations on Ships other than Liquefied Gas Carriers utilizing gas or other low flash point fuels CONTENTS 1. Application 2. Special Survey 2.1 Schedule 2.2 Scope
More informationEXPERIMENTAL SUPPORT OF THE BLEED AND FEED ACCIDENT MANAGEMENT MEASURES FOR VVER-440/213 TYPE REACTORS
International Conference Nuclear Energy for New Europe 22 Kranjska Gora, Slovenia, September 9-12, 22 www.drustvo-js.si/gora22 EXPERIMENTAL SUPPORT OF THE BLEED AND FEED ACCIDENT MANAGEMENT MEASURES FOR
More informationOsaka University Graduate School of Engineering Division of Global Architecture Dept. of Naval Architecture and Ocean Engineering Takuya Okubayashi,
Osaka University Graduate School of Engineering Division of Global Architecture Dept. of Naval Architecture and Ocean Engineering Takuya Okubayashi, Hiroyoshi Suzuki, Naomi Kato, Nagai Yoshiki, Hirokazu
More informationRULES PUBLICATION NO. 119/P
RULES PUBLICATION NO. 119/P PERIODIC SURVEYS OF FUEL INSTALLATIONS ON SHIPS OTHER THAN LIQUEFIED GAS CARRIERS UTILIZING GAS OR OTHER LOW FLASH POINT FUELS 2019 January Publications P (Additional Rule Requirements)
More informationSafety Standards for Decommissioning Activities
Safety Standards for Decommissioning Activities Koji OKAMOTO The University of Tokyo (Chair of AESJ Decommissioning Standard Committee) Status of decommissioning in Japan Nuclear Power Plant (NPP) under
More informationPOLICY & PROCEDURE #502 EFFECTIVE DATE: 6/5/02 LAST REVISED: 7/12/12 LAST REVIEWED: 7/8/15
1.0 PURPOSE PLANT OPERATIONS AND MAINTENANCE, CENTRAL PLANT PERSONNEL ARE RESPONSIBLE FOR USING THE IN ACCOMPLISHING THE VARIOUS JOB TASKS ESTABLISHED IN THEIR JOB DESCRIPTION. THIS POLICY AND PROCEDURE
More informationAnnual Report on Liquefied Petroleum Gas (LPG) Related Accidents
Annual Report on Liquefied Petroleum Gas (LPG) Related Accidents (13 version) The High Pressure Gas Safety Institute of Japan (KHK) Information Services & Research Department International Affairs Office
More informationINSTRUCTION MANUAL FOR MODEL 7360V VERTICAL CURING CHAMBER Revision E May
INSTRUCTION MANUAL FOR MODEL 7360V VERTICAL CURING CHAMBER Revision E May 2015 98-0520 S/N 2001 N. Indianwood Ave. Tulsa, Oklahoma 74012 U.S.A. TEL: (918) 250-7200 FAX: (918) 459-0165 E-mail: chandler.sales@ametek.com
More informationSAFE WORK METHOD STATEMENT Part 1 CONCRETE SAWING
SAFE WORK METHOD STATEMENT Part 1 CONCRETE SAWING Personal Protective Equipment Foot Hearing High Visibility Head Eye Face Hand Protective Clothing Breathing Normal Requirements: Safety footwear, hearing
More informationR2D2P. Working group report
R2D2P Working group report Working group members: Clédola Cassia Oliveira de Tello (Brazil), Farouk Abdel-Rahman (Egypt), Ibrahim Muhamad (Malaysia), Milan Vujovic (Serbia), Quang Huy Pham (Vietnam) Team
More informationThe Relationship Between Automation Complexity and Operator Error
The Relationship Between Automation Complexity and Operator Error presented by Russell Ogle, Ph.D., P.E., CSP rogle@exponent.com (630) 274-3215 Chemical Plant Control Control physical and chemical processes
More informationIAEA SAFETY STANDARDS for protecting people and the environment
Date: 2016-08-31 IAEA SAFETY STANDARDS for protecting people and the environment STATUS: STEP 8a For Submission to Member States DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS
More informationWaves Part II. non-dispersive (C g =C)
Waves Part II Previously we discussed Surface Gravity Waves Deep Water Waves Shallow Water Waves C g T 2 C g h dispersive (C g =C/2) Definitions: phase speed C= /T= /k non-dispersive (C g =C) group speed
More informationDESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS
SAFETY STANDARDS SERIES No. NS-G-1.10 DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS SAFETY GUIDE DS 482 2016-04-20 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, C-41 (May 13)
More informationTHERMODYNAMICS, HEAT AND MASS TRANSFER TUTORIAL NO: 1 (SPECIFIC VOLUME, PRESSURE AND TEMPERATURE)
THERMODYNAMICS, HEAT AND MASS TRANSFER TUTORIAL NO: 1 (SPECIFIC VOLUME, PRESSURE AND TEMPERATURE) 1. A vacuum gauge mounted on a condenser reads 66 cm Hg. What is the absolute pressure in the condenser
More informationGAS PIPELINE SAFETY GUIDE.
GAS PIPELINE SAFETY GUIDE. Date of issue 27/02/2017 Date of next review 27/02/2018 Page 1 Vector Limited 2017 Gas Pipeline Safety Guide February 2017 CONTENTS CONTENTS...2 WORKING SAFELY... 3 Your Legal
More informationNORMAL OPERATING PROCEDURES Operating Parameter Information
Operating Parameter Information Each operator performing the normal operating procedures (routine checks) of the facility should be familiar with the current normal operating parameters of all systems
More informationTHE LOVIISA NUCLEAR POWER PLANT DECOMMISSIONING PLAN UPDATE Matti Kaisanlahti NKS-R Decommissioning Seminar, Halden, Norway, November 2013
THE LOVIISA NUCLEAR POWER PLANT DECOMMISSIONING PLAN UPDATE 2012 Matti Kaisanlahti NKS-R Decommissioning Seminar, Halden, Norway, November 2013 Agenda Background Licensing Decommissioning schedule Decommissioning
More informationCP10 Sensor Installation and Maintenance Instructions
4030150/9 IM-P403-26 EMM Issue 9 CP10 Sensor Installation and Maintenance Instructions 1. Safety information 2. General product information 3. Installation 4. Maintenance 5. Spare parts Copyright 2017
More informationUnattended Bleeder Valve Thaws, Causing Fire
Unattended Bleeder Valve Thaws, Causing Fire Lessons Learned Volume 03 Issue 12 2004 USW Purpose Unattended Bleeder Valve Thaws, Causing Fire To conduct a small group lessons learned activity to share
More informationDESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS
SAFETY STANDARDS SERIES No. NS-G-1.10 DESIGN OF REACTOR CONTAINMENT STRUCTURE AND SYSTEMS FOR NUCLEAR POWER PLANTS SAFETY GUIDE DS 482 2016-04-20 INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA, C-41 (May 13)
More informationIMCA Safety Flash 10/11 September 2011
IMCA Safety Flash 10/11 September 2011 These flashes summarise key safety matters and incidents, allowing wider dissemination of lessons learnt from them. The information below has been provided in good
More informationSENSITIVITY ANALYSIS OF THE FIRST CIRCUIT OF COLD CHANNEL PIPELINE RUPTURE SIZE FOR WWER 440/270 REACTOR
PROCEEDINGS OF THE YEREVAN STATE UNIVERSITY Physical and Mathematical Sciences 216, 2, p. 57 62 P h y s i c s SENSITIVITY ANALYSIS OF THE FIRST CIRCUIT OF COLD CHANNEL PIPELINE RUPTURE SIZE FOR WWER 44/27
More informationModel PSI Compressor with 3-Gallon Air Tank 12VDC
Model 6350 150 PSI Compressor with 3-Gallon Air Tank 12VDC IMPORTANT: It is essential that you and any other operator of this product read and understandd the contents of this manual before installing
More informationEmergency Preparedness: Natural Disasters
Emergency Preparedness: Natural Disasters Natural disasters can strike anywhere and at any time, putting workers at risk for injuries and illnesses. Companies and workers may be required to deal with a
More informationNT09-21 Cruise Report SURUGA-BAY Cable Laying Experiment / VBCS Function Test
NT09-21 Cruise Report SURUGA-BAY Cable Laying Experiment / VBCS Function Test December 2009 Table of Contents 1. Overview 2. Schedule 3. Dive Summary 4. Concluding Remarks 1. Overview A unique development
More informationNT10-18 NATSUSHIMA / HYPER-DOLPHIN
NT10-18 NATSUSHIMA / HYPER-DOLPHIN Kumano-Nada October 2010 Earthquake and Tsunami Research Project for Disaster Prevention JAMSTEC TABLE OF CONTENTS 1. INTRODUCTION 2. SCHEDULE 3. DIVE RESULTS 4. CONCLUSIONS
More informationProposed Abstract for the 2011 Texas A&M Instrumentation Symposium for the Process Industries
Proposed Abstract for the 2011 Texas A&M Instrumentation Symposium for the Process Industries Focus Area: Automation HMI Title: Author: Shared Field Instruments in SIS: Incidents Caused by Poor Design
More informationOcean Observatories Initiative. Coastal & Global Scale Nodes. Hydrogen Safety. OOI Surface Mooring Hydrogen Safety Review
Ocean Observatories Initiative Coastal & Global Scale Nodes Hydrogen Safety CP01 Mooring Timeline: 21 November 2013: CP01CNSM was deployed and transitioned to shore controlled operations. 17 Feb. 2014:
More informationDDnmm,-- SEP U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Mail Stop OP1-17 Washington, D. C
SEP 0 5 2001 George T. Jones Vice President Nuclear Engineering & Support PPL Susquehanna, LLC Two North Ninth Street Allentown, PA 18101-1179 Tel. 610.774.7602 Fax 610.774.7797 gtjones@pplweb.com DDnmm,--
More informationPASSENGER SHIPS Guidelines for preparation of Hull Structural Surveys
(Feb 2010) PASSENGER SHIPS Guidelines for preparation of Hull Structural Surveys Contents 1 Introduction 2 Preparations for Survey 2.1 General 2.2 Conditions for survey 2.3 Access to structures 2.4 Survey
More informationSHUTDOWN SYSTEMS: SDS1 AND SDS2
Chapter 12 SHUTDOWN SYSTEMS: SDS1 AND SDS2 12.1 INTRODUCTION Up to this point we have looked with great details at the reactor regulating system. In order to better understand the overall design of a CANDU
More informationINSTALLATION OPERATION MAINTENANCE
Bermad Electrically Controlled On-Off Deluge Valve Model: 400E-3D INSTALLATION OPERATION MAINTENANCE Application Engineering BERMAD 1. Safety First BERMAD believes that the safety of personnel working
More informationSMART Explosion. Efficient Boiler Cleaning with Explosion Generators
SMART Explosion Efficient Boiler Cleaning with Explosion Generators Problem and Solution The use of solid fuels, such as coal, waste or biomass, is liable to intense fouling of the steam generator heating
More informationSiting and Installation Manual
Siting and Installation Manual B-Series Advanced Wastewater Treatment Units Revolutionary Waste Treatment Advanced Wastewater Treatment Units (ATUs) that deliver an unsurpassed performance at an unbeatable
More informationRISK ASSESSMENT & DISASTER MANAGEMENT PLAN
PAGE - 1 RISK ASSESSMENT & DISASTER MANAGEMENT PLAN 1.1 RISK ASSESSMENT A major accident in an industry has the potential to cause serious injury or loss of life and extensive damage to environment or
More informationResponding to Natural Gas Pipeline Emergencies
Responding to Natural Gas Pipeline Emergencies Who is Florida Gas Transmission? Florida Gas Transmission operates nearly 5,000-miles of interstate natural gas transmission pipelines, a system that extends
More informationPETROLEUM & GAS PROCESSING TECHNOLOGY (PTT 365) SEPARATION OF PRODUCED FLUID
PETROLEUM & GAS PROCESSING TECHNOLOGY (PTT 365) SEPARATION OF PRODUCED FLUID Miss Nur Izzati Bte Iberahim Introduction Well effluents flowing from producing wells come out in two phases: vapor and liquid
More information