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NRC and the nuclear industry to continue dialogue on Japan Task Force recommendations

The NRC has spent several weeks laying the groundwork for carrying out several recommendations of the agency’s Japan Near-Term Task Force, which looked at issues raised by the Fukushima nuclear accident in March. We’ve reached the point where we’re ready to start discussions with industry representatives and the public on how to best implement each of the recommendations.

The staff will hold its first implementation meeting this Thursday, Dec. 1, to discuss the recommendations that were subsequently categorized as “Tier 1,” or those to be implemented without unnecessary delay. The meeting will be held from 9 a.m. to noon in Room T2B3 of the Two White Flint North building at 11545 Rockville Pike, Rockville, Md. Visitors must use the NRC’s main entrance in the One White Flint North Building at 11555 Rockville Pike.

The staff and industry representatives will discuss the general approach to implementing the “Tier 1” recommendations. The public will have the opportunity to ask the NRC staff questions about the process during the meeting, which will be webcast. You can also participate by phone — call 888-469-1349 and use passcode 2977606.

The NRC will hold more meetings to lay out initial schedules and milestones for specific recommendations. The first few of these meetings have tentatively been scheduled at NRC Headquarters for Dec. 15; Jan. 5 and 19, 2012; and Feb. 2, 2012. Notices for these meetings will be posted on the NRC’s public meeting schedule.

The task force issued its report and recommendations on July 12. The Commission directed the staff to identify which recommendations could be implemented without unnecessary delay, and the staff responded with a proposal Sept. 9. The Commission provided direction to the staff on Oct. 18 on how to carry out the proposal.

Scott Burnell
Public Affairs Officer

5 responses to “NRC and the nuclear industry to continue dialogue on Japan Task Force recommendations

  1. Wasserfilter December 27, 2011 at 1:54 pm

    Hope the discussion will help to find a way to provide us with safe and reliable and payable energy …

  2. Paul December 16, 2011 at 5:55 am

    Fukushima Daiichi is dark point on the history of mankind. Government should take proper steps to ensure it do not happen again.

  3. Aladar Stolmar December 1, 2011 at 4:07 am

    Severe accident response for water cooled water moderated reactors
    Aladar Stolmar 11-14-24-2011
    Summary
    Considering the TMI-2, Fukushima Daiichi 1, 2 and 3 reactor severe accidents and the Paks-2 fuel washing vessel incident, also the SFD and other related nuclear reactor fuel severe damage experiments it is evident that the ignition and firestorm of the Zirconium-steam reaction occurs several hours after the severe reduction in cooling capability arises. This solution utilizes this time gap and proposes the equipment and response modifications aiming the elimination of ignition of Zirconium-steam reaction in PWR and BWR reactors. Also the solution deals with the results of such ignition and Zirconium-steam reaction in the maximum extent, in case the ignition despite the efforts occurs.
    Aiming the public safety in presence of nuclear power plant two questions have to be answered: Do You prevent the ignition of Zirconium in the steam? And Do You protect the surrounding of the plant from radioactive releases in case the entire Zirconium inventory burned in a firestorm? The presented here solution gives positive answers to both questions.
    The key element of this solution is the rapid reactor depressurization using a top vent from the reactor head. The same will provide a controlled routing for the Hydrogen generated in case the ignition of Zirconium-steam reaction still occurs.
    Recognizing the need for response
    It is very important to recognize that the condition for a severe accident response developed. The key characteristic for such a condition is the loss of reactor fuel cooling capability. The best demonstration of this is provided by the Paks refueling pond fuel washing vessel incident. The turning off the circulating pump required the switching on the natural circulation by removing the vessel head. Failure in the removing the washing vessel head after turning off the pump equals to loss of cooling capability. In TMI-2 the loss of cooling capability was caused by the loss of primary system coolant and hence the interruption of circulation through the core. The indicators were the temperature measurements from the core exit, – unfortunately ignored by the operators. In Fukushima Daiichi the loss of outside heat sink connection and continued heat transfer to the torus in form of exhaust from the turbine driven pumps caused overheating of water reserves and cavitations of the pumps and failure of coolant supply into the reactors. (In this later case the venting of exhaust from the turbine pump drives outside the torus also would increase the time, but there are reports of control failures as well due to loss of battery power.)
    It is necessary to develop a plant specific list of critical indicators, the detection of which will require to initiate the severe accident response.
    The guideline for developing such plant specific severe accident response trigger indicator list should start from inability to detect the reactor condition, go through the reactor circulation interruption and end with the loss of connection to the heat sink. Any of these should require immediate activation of Severe Accident Response.
    The means of Severe Accident Response
    It is a very simple high pressure vent line from the top of the reactor vessel to the outside environment, to the top of the vent stack or other high point. It must be equipped with a primary or inside the containment valve, which is locked open for the reactor operation and closed only for the reactor head removal and vent line disassembly during refueling operations; a Severe Accident Response Valve, which is in normal operating condition the only closing element between the top of the reactor and the environment and opened in response to the severe accident trigger indicator; a low pressure burst disc or blow away cap protecting the internal volume of vent pipe from the environment on the top end and a separator vessel with a float type condensate drain. The high pressure separator vessel should have a volume at least 10 times the internal volume of vent line and the incoming line should be the half diameter of the exhaust vent line, for example 100 mm reactor side and 200 mm vent stack side OD lines (also 100 mm OD separator drain) would be sufficient for a 500 MWe reactor system, 125 and 250 mm OD for 1000-1500 MWe.
    The location of the Severe Accident Response Valve should be close to a continuously manned operator workstation and the operators should be trained to open the Severe Accident Response Valve immediately, when instructed by the Unit Chief Shift Operator to do so. At the fill-up and pressurization (or cold shutdown depressurization) of reactor a manual 12 mm OD air-vent bypass line should be operated to assure the fill-up and drainage of the vent line before the Severe Accident Response Valve. The vent line between the reactor and Severe Accident Response Valve should drain back to reactor and drain to the separator after that.
    Borated water reserve and passive injection system is a standard element of nuclear power reactors, but a review of its operability in case of Severe Accident Response Valve activation and reactor system full depressurization should be mandated. The guideline for the acceptability of the system would be that a reactor from full power should be brought to cold shutdown using only these reserves as passive injection after opening the Severe Accident Response Valve. It is likely that addition of atmospheric pressure reserves located at higher elevations will be required in most of the NPPs.
    Normal response and recovery
    In case of the Severe Accident Response Valve activation even from a full power initial condition the reactor system would reach atmospheric pressure and the core would be continuously flooded by borated water, no extensive stagnant steam bubble formation in the core volume and ignition of Zirconium-steam reaction is expected. When the normal cooling and circulation is restored the Severe Accident Response Valve could be closed and after a detailed review the normal operation could be resumed. In case that an elevated coolant activity indicates some fuel cladding damage, the refueling and detailed fuel condition check should be performed before the normal operation recovery.
    Severe fuel damage and response
    In case the same severe fuel damage as in Fukushima Daiichi 1, 2 and 3 or TMI-2, – the ignition and firestorm of the Zirconium-steam reaction, – occurs the already open or subsequent opening of Severe Accident Response Valve will provide a vent line for the generated Hydrogen, where it most certainly will ignite and burn off. (Igniters could be provided to assure this.) The possibility to close the Severe Accident Response Valve after radioactivity detected in the vent line separator will allow a reduction of the radioactive releases into the environment. Periodic opening and closing of the Severe Accident Response Valve will provide means to reduce the containment pressure to safe levels for the expense of controlled radioactive releases.
    Additional safety concerns
    The routing of primary system outside the containment to the Severe Accident Response Valve could be viewed as a violation of the safety concept that the entire primary system should be enclosed in the containment. Providing an additional volume enclosing the vent line in a secure and controlled manner, which may include addition of isolator valves before and after the Severe Accident Response Valve will allow the sealing of primary system from the environment in case of leakages through Severe Accident Response Valve and a sealed volume connected to or separate from the containment will be formed what would resolve this concern. Indeed, this line should be treated as the most vital pipeline in the reactor system and should be provided with all the necessary anti-earthquake and other protections, most particularly freeze protection for the gas venting possibility. The operation of the reactor system could be allowed only when this system is fully operational, all isolator valves locked open. The sizing of this line should be based on water plug jets driven under the pressure difference from an explosive ignition and firestorm of the Zirconium-steam reaction.
    Civil defense and Severe Accident Response Team
    The actuation of Severe Accident Response Valve should be a trigger for the civil defense evacuation order in a predetermined extent and sequence, considering the downwind direction. The operators automatically become Severe Accident Response Team with a dedicated Recovery Outfit. In case the lost cooling capability and circulation through the core is verifiably restored, the head of the Severe Accident Response Team may order to close the Severe Accident Response Valve, which automatically switches the operation to a normal cold shutdown. The activated civil defense evacuation could be interrupted or ceased only based on the radioactive releases.
    Periodic tests
    The Severe Accident Response tests should be provided at least yearly for the operators and for the civil defense personal as mock tests, but a real test from 50% power also should be performed on each reactor after a full core reload and restart every 5 years. In order not to endanger the fuel integrity, the interruption of cooling is not required for the opening of Severe Accident Response Valve, only when the changing conditions in the reactor system require that. However, if elevated radioactivity of coolant would indicate fuel damage even in these conditions, a review of operating license is warranted. After the live tests the burst disks or blow away caps on the top of the vent pipe should be replaced!
    Rational of the severe accident response proposal
    The proposed manual valve operation in case of danger of severe accident in the nuclear power reactor system may be questioned based on the fact that we are deliberately venting into the air radioactive primary coolant or even fuel fragments containing Hydrogen reaction product in case the severity of the accident reaches the ignition of the fuel cladding and fuel bundle material, Zirconium ignition and complete burn off.
    The rational of the proposed response is based on the fact that in TMI-2 accident as well as in Chernobyl-4 and Fukushima Daiichi 1,2 and 3 reactor accidents the burn off of the Zircalloy was very extensive and the produced Hydrogen in TMI-2 did not cause the demolition of the containment, but in other two nuclear power plants – four reactors! – the uncontrolled evacuation of Hydrogen and detonation of Hydrogen-air mixture destroyed the reactor buildings, making very difficult the localization and recovery. A timely opening of the manual response valve and fast depressurization of reactor system has a good chance to prevent of the ignition of Zirconium in the steam at all. Also the possibility of closing the same valve in case the radioactivity release detected provides new means of reducing the environmental releases, prevents the building demolition by allowing the lowering of pressure, venting the generated hydrogen. In short the rational is in the localization of consequences of the severe accident by preserving the integrity of reactor containment and preventing the severe accident at all by the actions of operators and for the expense of limited radioactive releases.
    The argument that by adding such a response valve and its tests endanger the closure of radioactivity within the fuel bundles have to be rejected based on the requirement to the fuel cladding. It has to withstand such loads. And it has to be periodically demonstrated, as proposed. If there is damage to the fuel as a result of the periodic tests, the fuel supplier has to be responsible.
    An obvious question that since we are adding new means, a new vent line from the reactor why not equip this line with all the necessary filtration for the worst case scenario? For new plant design such a consideration is valid, however this solution is general, for existing plants as well and the cost implications for a 5 or 10 year remaining life of a plant does not necessarily justify such expenses for a system, which will never be used, except the test.
    Scenarios
    Periodic test
    After the first time the 50% of power achieved on a new or fully reloaded reactor a full scale test of the Severe Accident Response have to be performed, including the Civil Defense evacuation procedure. It is necessary to demonstrate that the reactor, the plant personnel and the public are capable to handle the most severe conditions possible and the severity for the environment is under control. This test is performed with manual reactor shut down (SCRAM) and Severe Accident Response Valve opening. The test is successful if the atmospheric pressure is achieved in the reactor and the atmospheric borated water injection starts. At that point the Severe Accident Response Valve could be closed, the normal operation of the reactor resumed after the blow away cap or burst disc replaced on the vent line. During the test the normal pressure relief and make-up and drain lines could be operated to speed-up the pressure reduction and cool down, and this is a test of all emergency cooling systems as well.
    Inability to detect the reactor condition
    An unlikely condition when the information from the reactor telemetry is lost or corrupted. The response is performed with manual reactor shut down (SCRAM) and Severe Accident Response Valve opening and Civil Defense alarm. The Severe Accident Response can be interrupted after the reactor condition detection is restored and the circulation through the reactor core is verified or the cold shutdown is achieved. The rational to use the Severe Accident Response Valve to control the reactor is the fact that the opening of the Severe Accident Response Valve reduces the pressure inside the reactor core which causes the boiling of the cooling water and the steam replacing the water within the core reduces the energy loss of neutrons, therefore reducing the reactivity on the thermal neutrons and shuts down the chain reaction, even if the SCRAM would fail for any reason in the PWR and BWR reactors. Also the opening of the Severe Accident Response Valve and venting the steam from the top of the reactor vessel organizes a flow stream through the core from the bottom to the top, mimicking the circulation in normal cooling condition, even if that circulation is interrupted. The differential evaporation of boric acid assures a safe shutdown on its own, but the quick reduction of pressure to the actuation of accumulators with elevated Boron concentration finishes the shutdown of chain reaction by flooding the core with cold borated coolant. A prolonged cooling of the core is assured by the atmospheric borated emergency coolant reserves injection into the core under the gravity.
    Reactor circulation interruption
    In the event the forced circulation through the core is lost a stagnant steam bubble can form in the core and lead to the Zirconium ignition and complete burn off. The response is performed with manual reactor shut down (SCRAM) and Severe Accident Response Valve opening and Civil Defense alarm. The Severe Accident Response can be interrupted after the circulation through the reactor core is verified or the cold shutdown is achieved. The rational to use the Severe Accident Response Valve to control the cooling of the reactor is the fact that the opening of the Severe Accident Response Valve vents the forming steam and reduces the pressure inside the reactor core which causes the boiling of the cooling water and the steam replacing the water within the core reduces the energy loss of neutrons, therefore reducing the reactivity on the thermal neutrons and shuts down the chain reaction, even if the SCRAM would fail for any reason in the PWR and BWR reactors. Also the opening of the Severe Accident Response Valve and venting the steam from the top of the reactor vessel organizes a flow stream through the core from the bottom to the top, mimicking the circulation in normal cooling condition, even if that circulation is interrupted. The differential evaporation of boric acid assures a safe shutdown on its own, but the quick reduction of pressure to the actuation of accumulators with elevated Boron concentration finishes the shutdown of chain reaction by flooding the core with cold borated coolant. A prolonged cooling of the core is assured by the atmospheric borated emergency coolant reserves injection into the core under the gravity.
    Loss of connection to the heat sink
    As a lesson learned from the loss of Fukushima Daiichi 1, 2 and 3 reactors an event when the cooling with an outside heat sink is ceased to function is considered. The response after the reactor is shut down is performed with manual Severe Accident Response Valve opening and Civil Defense alarm. The Severe Accident Response can be interrupted after the connection to the outside heat sink is restored and the circulation through the reactor core is verified or the cold shutdown is achieved. The rational to use the Severe Accident Response Valve to control the cooling of the reactor is the fact that the opening of the Severe Accident Response Valve vents the forming steam from the top of the reactor vessel and organizes a flow stream through the core from the bottom to the top, mimicking the circulation in normal cooling condition, even if that circulation is interrupted. The differential evaporation of boric acid assures a safe shutdown on its own, but the quick reduction of pressure to the actuation of accumulators with elevated Boron concentration finishes the shutdown of chain reaction by flooding the core with cold borated coolant. A prolonged cooling of the core is assured by the atmospheric borated emergency coolant reserves injection into the core under the gravity.

  4. Alise Keough November 30, 2011 at 11:40 pm

    “The meeting will be held from 9 a.m. to noon in Room T2B3 of the Two White Flint North building at 11545 Rockville Pike, Rockville, Md. Visitors must use the NRC’s main entrance in the One White Flint North Building at 11555 Rockville Pike.”

    Will this meeting be televised or shown on the web? Or even recorded? Just curious, it seems like this would be vital information, especially for those of us that live in the Pacific Northwest.

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