nakos said:
Dear members of this forum!
I have just registered here and didnt follow all 700+ pages of this discussion. Howerver, i participate actively on russian analog of this topic on site atominfo.ru which now is about to turn 600+ pages. I would like to ask someone here to give me brief summary on what you think on few questions that caused controversy among us in Russia:
1. hydrogen flow path from PCV into confinements: leakage? Vented into reactor hall on purpose? Backflow? Commonalities in units 1-2-3?
2. hydrogen flow unit 4: TEPCO explanations credible?
3. what is your intuition on conditions of RPVs? Total lower plenum breach or "leakage" only?
4. Where did Unit 2 blow up? S/C?
5. Unit 1 IC failure mode?
6. Units 2,3 RCIC failure mode: S/C saturation?
7. SFP fuel damage? Any at all?
8. Very specific question on hardened vent in Unit 1.
Is it possible to tell if MO210 valve is normally open or closed? Other valves? Purpose of rupture disc if we decide valve is in closed position?
More questions coming. Thank you all.
My ideas: partly guesses, partly on more solid ground:
1. Leakage past containment lid seals is probably one route, since it has been reported on several occasions that they tend to leak even during regular containment pressure testing (around 5 bar), and during the accident, the PCV pressures exceeded 8 bar.
2. I would not say it's impossible, and the higher contamination on the outside of the SGTS filters as compared to the inside filters seems to support this idea.
3. Main circulation pump seals are probably leaking at all units. In addition to that, Unit 1 appears having depressurised during the late evening of March 11, which possibly indicates a leak from the bottom of the RPV. Boiling water reactor bottom plenum is not expected to completely breach even in severe accidents - it is more probable that some instrumentation tubes and/or control rod penetrations fail first and let the corium flow out. Other units than 1 - hard to say, since in my opinion we don't even have a good idea of the extent of the core damages.
5. According to the TEPCO report to the IAEA, it appears that the unit 1 IC did not fail at all: it just was not used. At 15:03 on March 11, they closed the IC valve and at 15:07 activated the HPCI; after the tsunami the HPCI failed, but the IC was not reactivated. Around 18:18-18:25 they briefly opened the IC valve, but closed it again for another 3 hours. Around 18:30 there would probably have been so much hydrogen in the reactor, that the steam was not able to enter the IC any more. In the recent video it was shown how the water gauges at the IC:s show the tanks still to be 70 % full.
6. A plausible explanation, although I have not been able to get verification.
7. The results given in April on the unit 4 pool water samples indicate very limited (if any) damage to unit 4:s spent fuel. At Unit 3, there probably are failures in the pool due either the hydrogen explosion or the subsequent uncovery.
8. According to the TEPCO reports to the IAEA, the MO210 valve seems to be normally closed and has to be opened as part of preparations for venting. All in all, it seems a very complicated procedure, with DC current needed for the said valve, compressed air for the other valve, and the containment pressure must be high enough to break the rupture disc. My uneducated guess is, that since there's no scrubbing or filtration in the pressure relief line, they have tried to make spurious initiation of the venting improbable by providing the multiple obstacles. Which turned out catastrophical, since the failure to vent the containments in the severe accident conditions delayed the capability to pump in firefighting water and most probably made the core damages much worse than they would have been if the pressure reduction would have taken place sooner. (Another contributing factor seems to have been the design of the reactor pressure relief lines, which also require both DC current and compressed air to function, and the delay to relieve reactor pressure after the failure of the RCIC/HPCI systems seems in my opinion to have been the most significant single factor contributing to the core damages at units 2 and 3.)
I am no expert in GE BWRs (consider myself somewhat of an expert on the ASEA line of BWRs, however), and have followed the events from the other side of the globe mainly through NHK, TEPCO's reports and the wonderful contributions of Tsutsuji-san, so the answers above are not to be taken as anything more than just my personal impressions based on the data I've been able to get.