Japan Earthquake | Page 2940

  • hairoaction.com is rather interesting. I had to machine translate the site but they have action efforts for exposed workers, breastfeeding mothers, childrens exposure etc.
    by lillymunster 2/2/2012 9:28:22 PM

  • @dean I think that is a good idea. What each group's main focus is, efforts underway etc.
    by lillymunster 2/2/2012 9:29:06 PM

  • @dean sent you a gmail
    by lillymunster 2/2/2012 9:30:10 PM

  • k
    by dean 2/2/2012 9:30:36 PM

  • reply
    by dean 2/2/2012 9:37:20 PM

  • @dean , @lilly, after the Niigataken Chuetsu-Oki Earthquake in 2007 and the seismic damage evaluation that followed at Kashiwazaki-Kariwa NPP, the NRC must have recommended to the operators in quake-prone regions of the US to install some seismic upgrades. E.g., snubbers were installed at North Anna npp. I don't know what the operators near Savannah implemented. The region seems more active than Central Virginia. It seems worthwhile to keep an eye on whether and to what extent the NRC-recommended upgrades have actually been implemented in US plants.
    by Peter 2/2/2012 9:37:29 PM

  • @Peter good comments.. to complicate matters further the NRC recently will issue new guidance with the help of USGS to provide new rules on NPP locations between the east and west part of the country. thats one problem, the USGS comes up with new seismic assumptions that then have to be fed through complicated analyses and it is hard to keep up with determining what must be done at each plant based on the USGS data and then implement some sort of timeline schedule to get the modifications etc completed and upgrades to the TSR...
    by dean 2/2/2012 9:41:11 PM

  • @Peter right now the NEI is busy trying to get the NRC safety upgrades watered down and delayed. They really need to get them 100% official in writing with dates and sent to operators. Otherwise the post-Fuku safety changes will end up undone for decades. I worry the seismic updates coming could get the same treatment.
    by lillymunster 2/2/2012 9:41:38 PM

  • More on San Onofre. Now they think all 3 units may have steam generator problems. The damaged unit has ruined pipes in the steam generator. They replaced these all in 2010. enformable.com
    by lillymunster 2/2/2012 9:47:26 PM

  • Someone is asking me about Unit 1 pressure before the explosion. I seem to recall there used to be links to the raw data feeds for the reactor parameters in the sticky notes, but I can't find them now. I should have links on my other computer. Edano's graph is good www.houseoffoust.com but it's nice to have explicit numbers.

    by Ian via Houseoffoust 2/2/2012 9:47:57 PM

  • Sorry, I hate how you can't sometimes just cite a graphic w/o posting it.
    by Ian 2/2/2012 9:48:45 PM

  • reply @ lilly
    by dean 2/2/2012 9:49:40 PM

  • @Ian are you looking for the CSV file?
    by lillymunster 2/2/2012 9:52:16 PM

  • enformable.com to a independent panel of experts, power generation at Chubu Electric Power Co.’s Hamaoka nuclear plant costs more than that at its thermal power plants. The estimated 9.78 yen per kilowatt-hour cost exceeds a minimum cost of 8.9 yen the national government has estimated for nuclear power plants.
    by dean 2/2/2012 10:00:47 PM

  • Power Reactor Event Number: 47628
    Facility: SAN ONOFRE
    Region: 4 State: CA
    Unit: [ ] [ ] [3]
    RX Type: [1] W-3-LP,[2] CE,[3] CE
    NRC Notified By: DOUG FOOTE
    HQ OPS Officer: JOHN KNOKE Notification Date: 01/31/2012
    Notification Time: 22:58 [ET]
    Event Date: 01/31/2012
    Event Time: 17:30 [PST]
    Last Update Date: 01/31/2012
    Emergency Class: NON EMERGENCY
    10 CFR Section:
    50.72(b)(2)(iv)(B) – RPS ACTUATION – CRITICAL Person (Organization):
    JEFF CLARK (R4DO)
    SCOTT MORRIS (IRD)
    LOUISE LUND (NRR)
    Unit SCRAM Code RX CRIT Initial PWR Initial RX Mode Current PWR Current RX Mode
    3 M/R Y 100 Power Operation 0 Hot Standby
    MANUAL TRIP DUE TO A PRIMARY TO SECONDARY LEAK GREATER THAN 30 GAL/HR”At 1505 PST, Unit 3 entered Abnormal Operation Instruction S023-13-14 ‘Reactor Coolant Leak’ for a steam generator leak exceeding 5 gallons per day.”At 1549 PST, the leak rate was determined to be 82 gallons per day. At 1610 PST, a leak rate greater than 75 gallons per day with an increasing rate of leakage exceeding 30 gallons per hour was established and entry into S023-13-28 ‘Rapid Power Reduction’ was performed.”At 1630 PST, commenced rapid power reduction per S023-13-28 ‘Rapid Power Reduction’. At 1731 PST, with reactor power at 35% the Unit was manually tripped. At 1738 PST, Unit 3 entered Emergency Operation Instruction S023-12-4 ‘Steam Generator Tube Rupture’.”At 1800 PST the affected steam generator was isolated.”All control rods fully inserted on the trip. Decay heat is being removed thru the main steam bypass valves into the main condenser. Main feedwater is maintaining steam generator level. No relief valves lifted during the manual trip. The plant is in normal shutdown electrical lineup.Unit 2 is presently in a refueling outage and was not affected by this event.The licensee has notified the NRC Resident Inspector. The licensee has issued a press release.
    by dean 2/2/2012 10:03:49 PM

  • San Onofre... problems... in 2011
    by dean 2/2/2012 10:04:20 PM

  • This was not the first time a leak-scare has occurred at the San Onofre plant. In November 2011, a level 1 alert was issued at the plants but the appropriate alarms did not go off.

    San Onofre just finished replacing both steam generators attached to Unit 2 and 3. Many other plants of similar design have conducted similar upgrades, but none, according to the NRC, has had a rupture after being installed.

    The leak is not Edison’s first problem with the new steam generators.

    In September 2009, Edison met with NRC officials to discuss weld defects that were detected in both of the 640-ton crucibles.

    The utility notified the NRC in August 2009 that the replacement generators for Unit 3 had developed cracks in a weld that connects a 5-inch-thick steel plate that supports each generator’s innards.

    Inspections found that use of a special metal-gouging tool caused the welds to become brittle and crack. Mitsubishi Heavy Industry, the company that built the generators for Edison, fixed the cracked welds, and they passed NRC inspection.
    by dean 2/2/2012 10:04:47 PM

  • by dean 2/2/2012 10:05:07 PM

  • Sounds like San Onofre will be down for a long time while they sort this out. Does anyone know when the CA nuclear referendum vote will be or if they have enough signatures to get it on the ballot?
    by lillymunster 2/2/2012 10:06:38 PM

  • Wired joins Asianweek in debunking the stone Iran conspiracy theory:Jim Stone, a self-professed former National Security Agency analyst with an “engineering background,” has a different explanation: The whole thing was a deliberate and dastardly act of nuclear war
    www.wired.com Interesting the theory portrays Israel as aggressor, and Iran as victim.
    by artnuke 2/2/2012 10:16:53 PM

  • Newest F-35s grounded because ejection parachutes installed backwards. This would never happen on a nuclear power plant... would it? www.airforcetimes.com
    by artnuke edited by elainekirk 2/2/2012 10:20:36 PM

  • @lilly.. gmails
    by dean 2/2/2012 10:55:52 PM

  • @dean thanks.
    by lillymunster 2/2/2012 10:58:02 PM

  • will return later @all.. great day for exchange
    by dean 2/2/2012 11:01:31 PM

  • @Ian raw data: www.tepco.co.jp the pressure data is in columns 4-8 (3rd after date column)
    by Edano 2/2/2012 11:15:56 PM

  • WASHINGTON — The Nuclear Regulatory Commission said Wednesday that it had rejected some of the Indian Point nuclear power plant’s procedures for assuring fire safety, noting that its two reactors lacked some equipment that was typically used to meet the commission’s regulations. www.nytimes.com
    by elainekirk 2/2/2012 11:35:33 PM

  • Steam Dump Control - The steam dump control system reacts to prevent a reactor trip following
    a sudden loss of electrical load. The steam dump control system also removes stored energy and
    residual heat following a reactor trip so that the plant can be brought to equilibrium no-load
    conditions without actuation of the steam generator safety valves. The steam dump control system
    also provides for maintaining the plant at no-load or low-load conditions to facilitate a controlled
    cooldown of the plant.
    Rapid Power Reduction - For large, rapid load rejections (turbine trip or grid disconnect from
    50-percent power or greater) a rapid nuclear power cutback is implemented. This results in a
    reduction of thermal power to a level that can be handled by the steam dump system.
    by dean 2/3/2012 12:21:57 AM

  • definition of a rapid power reduction,,, good terms to understand and why they do them.. at large PWR or BWR plants..
    by dean 2/3/2012 12:22:25 AM

  • Rapid Power Reduction Rod Selection
    The number of rods needed to obtain this power reduction is dependent on the core burnup during
    the fuel cycle. In addition, if a large load rejection (grid disconnect) is initiated at a part-power
    condition (50-percent to 100-percent power), then a reduced number of control rods need to be
    released. Therefore, a means is provided to have the control system select which rods will be
    released by the rapid power reduction system.
    The selection of the rods that are released during the rapid power reduction is based on a thermal
    power measurement. The thermal power is integrated over time to arrive at a core burnup.
    Depending on the core burnup and the plant power level, the choice of the control rods to be
    released by the rapid power reduction system is determined. Capability is provided for the
    operator to correct the integrated burnup periodically based upon a more detailed burnup
    calculation.
    by dean 2/3/2012 12:24:31 AM

  • MANUAL TRIP DUE TO A PRIMARY TO SECONDARY LEAK GREATER THAN 30 GAL/HR

    "At 1505 PST, Unit 3 entered Abnormal Operation Instruction S023-13-14 'Reactor Coolant Leak' for a steam generator leak exceeding 5 gallons per day.

    "At 1549 PST, the leak rate was determined to be 82 gallons per day. At 1610 PST, a leak rate greater than 75 gallons per day with an increasing rate of leakage exceeding 30 gallons per hour was established and entry into S023-13-28 'Rapid Power Reduction' was performed.

    "At 1630 PST, commenced rapid power reduction per S023-13-28 'Rapid Power Reduction'. At 1731 PST, with reactor power at 35% the Unit was manually tripped. At 1738 PST, Unit 3 entered Emergency Operation Instruction S023-12-4 'Steam Generator Tube Rupture'.

    "At 1800 PST the affected steam generator was isolated."

    All control rods fully inserted on the trip. Decay heat is being removed thru the main steam bypass valves into the main condenser. Main feedwater is maintaining steam generator level. No relief valves lifted during the manual trip. The plant is in normal shutdown electrical lineup.

    Unit 2 is presently in a refueling outage and was not affected by this event.

    The licensee has notified the NRC Resident Inspector. The licensee has issued a press release.
    by dean 2/3/2012 12:27:13 AM

  • shows the criteria for reportable leak rates 5 gallons per day.. abnormal operation instruction s023-13-14, then leak increased with the increasing leake rate in excess of 30 gal/hour... pushed them into rapid power reduction and subsequent NRC and other notification
    by dean 2/3/2012 12:29:12 AM

  • PWR's usually like to ramp power down in lieu of a scram because it's less stressful on core internals
    by dean 2/3/2012 12:30:07 AM

  • www.edison.com Contact: Media Relations, (626) 302-2255

    ROSEMEAD, Calif., Feb. 1, 2012 � Southern California Edison (SCE), operator of the San Onofre Nuclear Generating Station, continues to plan for the repair of the steam generator tube leak in Unit 3 following a precautionary shutdown Tuesday. Sensitive monitoring instruments at Unit 3 continue to show no change in radiation levels that would be detectable off-site.

    Operators responded quickly yesterday to indications of a steam generator tube leak based on readings from highly sensitive instruments designed to detect this condition, and in time to take action to prevent any potential change in detectable radiation exposure outside the plant boundary. Operators safely shut the plant down and isolated the component that contained the leaking tube within four hours of detecting the indications.

    Currently, operators are cooling down Unit 3 and reducing pressure in the plant, which is the method to stop the tube from leaking. They are meticulously following prescribed procedures written specifically for addressing a tube leak condition.

    "There was no threat then, nor is there now any danger to the public or to plant workers," said Pete Dietrich, senior vice president and Chief Nuclear Officer for Southern California Edison. "Our operators performed exactly as they are trained to perform and took prompt action to ensure we did not create a situation involving any challenge to the health and safety of the public," Dietrich said.

    Unit 2 is currently offline for a planned maintenance, refueling and technology upgrade outage. Service will not be affected; Southern California Edison has ample reserve power to meet customer needs.
    by dean 2/3/2012 12:33:03 AM

  • www.rolls-royce.com the global power systems company, has won a €250 million contract with AREVA to supply safety instrumentation and control (I&C) technologies and systems for the French nuclear reactor modernisation programme. The systems will be installed in the twenty-strong French fleet of 1300 MW nuclear reactors operated by Electricité de France
    by dean 2/3/2012 12:35:57 AM

  • hi Dean!
    by lillymunster 2/3/2012 12:50:09 AM

  • hi @lilly
    by dean 2/3/2012 12:51:57 AM

  • www.urscorp.com West (SGT), a URS/AREVA NP joint venture company, is providing project management, planning, engineering and construction services to prepare and install four new steam generators each at Units 1 and 2 at Diablo Canyon Nuclear Power Plant, which is located near Avila Beach along the central California coast, for the Pacific Gas and Electric Company of San Francisco. The plant provides electricity for approximately three-million households in northern and central California.
    by dean 2/3/2012 12:55:40 AM

  • @lilly... with areva name I wonder if they will be mitsubishi steam generators
    by dean 2/3/2012 12:56:37 AM

  • very large expensive endeavor

    by dean 2/3/2012 12:57:30 AM

  • @dean They already did the upgrades IIRC. It is the new ones that are now failing. I bet this will end up in court. I wonder how many more of that steam generator could be at other plants?
    by lillymunster 2/3/2012 1:05:56 AM


  • @lilly.. true.. the article had the steam generator and I wondered if it had a mitsubishi sign on it
    by dean 2/3/2012 1:07:29 AM

  • www.mhi.co.jp Steam Generator Schematics(Model 70F-1)
    by dean edited by lillymunster 2/3/2012 1:10:45 AM

  • Bird life badly hit by nuclear fallout in Japan www.irishtimes.com
    by lillymunster 2/3/2012 1:30:40 AM

  • total loss of animal life is probably horrendous @lilly
    by dean 2/3/2012 1:33:48 AM

  • @dean I don't know of anyone specifically studying wildlife in the zone. I am sure someone is. The domestic animals, it is hard to tell what is lack of food/shelter vs. radiation contributing to death and illness.
    by lillymunster 2/3/2012 1:42:27 AM

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