Mihama Unit 3 Pipe Rupture (2004): Thinning Downstream of an Orifice
On August 9, 2004, a secondary-system condensate pipe in the turbine building of Kansai Electric Power’s Mihama Unit 3 ruptured; five people working nearby were killed by the escaping steam and hot water and six were injured. The rupture was downstream of a flow-measuring orifice, where erosion–corrosion had thinned the carbon steel wall from its original 10 mm to 0.4 mm at the thinnest point. The location had been missing from the wall-thickness inspection list from the start.
What happened
- Date
- August 9, 2004, at about 15:28
- Location
- Turbine building of Mihama Unit 3, Kansai Electric Power Co., Japan
- Pipe
- Secondary condensate pipe (loop A, from the No. 4 low-pressure feedwater heater to the deaerator), downstream of a flow-measuring orifice. Carbon steel (SB42), outside diameter 558.8 mm, nominal wall 10 mm
- Conditions
- About 140 °C, 0.93 MPa, flow 1,700 m³/h (design conditions 195 °C, 1.27 MPa)
- Wall thickness
- 0.4 mm at the thinnest point of the rupture (minimum required by the technical standard: 4.7 mm)
- Casualties
- 5 killed, 6 injured
- Investigation
- Nuclear and Industrial Safety Agency (NISA), final report on the secondary piping rupture at Mihama Unit 3, March 30, 2005
Sequence of events and the investigation’s findings
The accident occurred during preparations for the unit’s 21st periodic inspection, when a total of 105 people were working in the building. Workers near the ruptured pipe were exposed to the escaping steam and hot water. The reactor shut down automatically in response to the secondary-system leak.
The rupture opening measured about 515 mm in the axial direction and about 930 mm around the circumference. The crack is reported to have grown first in the axial direction and then around the circumference. According to an information notice of the U.S. Nuclear Regulatory Commission (NRC), the same location on the loop B pipe was 1.8 mm thick.
The chain of causes from the materials side
The final report concluded that the pipe wall gradually thinned during operation by so-called erosion–corrosion until it lacked strength and ruptured. The orifice constricted the flow, exposing the pipe wall downstream to turbulent flow. The nuclear industry also calls this phenomenon flow-accelerated corrosion (FAC). The NRC noted that the inner surface of the rupture showed a fish-scale-like pattern while the bottom of the pipe kept its nominal thickness, which it described as characteristic of flow-accelerated corrosion.
Flow-accelerated corrosion proceeds as iron oxide on the surface of carbon steel dissolves into the flowing water and is carried away by the turbulent flow. According to a presentation published by the UK Institute of Corrosion, the thinning rate varies with temperature in a bell-shaped curve (peaking at about 140–160 °C in single-phase water flow), is faster at lower pH, and slows as the chromium content of the steel increases.
The rupture location had already been left off the list when Mitsubishi Heavy Industries prepared the inspection list under the PWR management guidelines in 1990, so the thinning beyond the usable limit went unnoticed. Registration omissions numbered 3 at Mihama Unit 3 and 42 across Kansai Electric’s 11 units. Japan’s White Paper on Nuclear Energy identified the root cause as a wall-thinning management error involving three companies (Kansai Electric, Mitsubishi Heavy Industries and Nihon Arm), in which locations needing management were missing from the original list and were not corrected before the accident.
The clues that revealed the cause
- The wall at the rupture had thinned locally to 0.4 mm Deformation at the fracture: Material was lost before …
- The inner surface showed a fish-scale-like pattern (NRC) Fracture surface and crack features: Inner surface scalloped l…
- The flow was disturbed downstream of the orifice Environment: Fast flow, droplets or pa…
- The pipe was carbon steel Material: Ordinary carbon or low-al…
- Water at about 140 °C was flowing Service temperature: Moderate (about 60–300 °C…
- The unit had operated since 1976 Time to failure: Years or more
Open the guide with this case’s clues
Opening the guide with these clues ranks flow-induced wall thinning at the top.
Related failure modes: Flow-induced wall thinning (erosion–corrosion)
What changed afterwards: design, rules and inspection
- The guidelines for managing pipe wall thinning at pressurized water reactor plants (the PWR management guidelines) were revised and the management methods clarified.
- The government asked the Japan Society of Mechanical Engineers (JSME) to develop a standard for pipe wall thickness management and to use it promptly as a basis for safety regulation. The JSME issued the Rules on Pipe Wall Thinning Management (JSME S CA1-2005) and, in 2006, technical rules for pipe wall thinning management at PWR and BWR plants (JSME S NG1-2006, JSME S NH1-2006).
- The ordinance under the Electricity Business Act was revised to clarify the scope and methods of periodic licensee inspections.
- The utility took measures against recurrence, such as spreading its management policy and reorganizing, and the manufacturer revised its measures against registration omissions and its quality assurance system.
Lessons
- Wall thinning is local and hard to predict. Measure first where flow is disturbed, such as downstream of orifices and tees.
- Every location to be inspected must be registered, with a system for finding and correcting omissions. Here the original omission went uncorrected for more than a decade, until the accident.
- Even a small amount of chromium in steel slows flow-accelerated corrosion. Replacing a pipe is an opportunity to reconsider the material.
- The same damage occurs in thermal power and petrochemical plants, so countermeasures need to be shared across industries.