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Last login: Tuesday, September 11, 2012
PART 1 - COMPARING SONGS UNIT 2 RESTART WITH MIHAMA, FUKUSHIMA DAIICHI AND CHERNOBYL NUCLEAR DISASTERS
At around 13: 50, on February 9th, 1991, leakage of about 55 tons of primary coolant occurred due to the failure of one SG tube in a steam generator built by Mitsubishi in the No. 2 pressurized water reactor at the Mihama nuclear power station in Japan. This accident was the first level three nuclear disaster in Japan. Therefore, this accident caused social concerns in Japan with the unsafe operation of nuclear reactors. For example, level one is a minor event, and level seven is major accident. The loss of coolant that occurred in Three Mile Island was ranked level five. The level number increases with the scale of the accident. Fukushima Daiichi and Chernobyl Nuclear Disasters were level seven major accidents.
SONGS NRC AIT Inspection Report States, “The replacement steam generator design developed by Mitsubishi for SONGS Unit 2 and Unit 3 in accordance with the licensee’s design specification was translated into the same set of design and fabrication drawings. The team noted that some as-built dimensions varied between Unit 2 and Unit 3 steam generators as a result of the divider plate weld repairs in Unit 3 and other manufacturing processes. However, these dimensional changes did not represent significant deviations from the original design specifications. The result of the independent NRC thermal-hydraulic analysis indicated that differencesin the actual operation between units and/or individual steam generators had aninsignificant impact on the results and in fact, the team did not identify any changes in steam velocities or void fractions that could attribute to the differences in tube wear between the units or steam generators. It should be noted that increases in primary temperature and steam generator pressures has the effect of reducing void fractions and peak steam velocities, which slightly decreases the conditions necessary for fluid elastic instability and fluid-induced vibration.
Note: For Continuation see Part 2
September 12, 2012 at 9:13 a.m.
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SCE Website SaysUnit 3 Steam Generator Tube Leak = Cause of Unexpected Tube-to-Tube Wear •Specific mechanism is Fluid Elastic Instability causing excessive tube vibration –Most excessive wear occurring in limited area of Unit 3 steam generators •This is due to: •High steam flow velocities •Very dry steam •Inadequate tube support structure in the U bend region for the tubes experiencing the wear Questions To SCE are as followsWho designed the Generator Mitsubishi or the SCE Steam Expert, who wrote the Paper about SCE/MHI Challenging Rewards/Innovative Designs and team work?According to SONGS Root Cause Guru, SCE Steam Expert wrote the defective specifications and MHI Says to other Root Cause Guru, we listened to the Great SCE Steam Guru and built these Wonderful Steam Generators. MHI Says SCE did not know how to Operate these Wonderful Radiation Steaming Crucibles and SCE put too much steam to generate too much power and broke it. SCE Guru also says if SCE Steam Expert had asked their dear Counter Parts at Palo Verde about the steam generators, they would have told them to go to Westinghouse. Now the Generators are broke. SCE Should Retire Units 2 and 3 Steam Generators into an exhibition in Parking Lot 4 by the Beach and follow the example of Mihama, so they can learn from their catastrophic mistakes . SCE Officials should make their honest living from the public donations by showing them the broken generator instead of charging the rate payerscatastrophic mistakes .
September 11, 2012 at 7:48 p.m.
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