ASME NML-1 pdf free download

ASME NML-1-2019 pdf free download.Rules for the Movement of Loads Using Overhead Handling Equipment in Nuclear Facilities.
cascading failures: a process In a system of Interconnected parts in which the failure of one or a few parts can trigger the (allure of other parts and so on.
design ivied torque: the torque required to hold the design rated load of the hoist at the point oF brake appbcatlon.
double-rigging arrangement a system in which two independent sets of load-carrying elements, each capable of carrying the load, are used to connect the load to the overhead handling equipment.
emergency response plan.’ a set olaL-tions necessary to mitigate the consequences of the worst possible outcomes ola Ioad•handhng accident.
engineered temporary lift assembly (ETL.4): specially designed lifting equipment that Is not general purpose but has a special temporary Intended purpose. These assemblies are not standard design items and are not available from a commercial source, and there Is no generally accepted consensus standard appikable to the equipment. Examples of ETLAs Include special gin poles and derricks; special crane supports SUCh as runways or overhead gantry columns and frames; and special load-han. dling equipment such as up-end and down-end devices and jacking towers (unless used with the guidance of the applicable volume of ASME B30). ETLAs are required for lifts that cannot be accomphshed with standard lifting devices.
essential witty unctaon (LSF: a function performed by a plant system, structure, or component that is necessary to remove decay heat From irradiated fuel, provide shielding. contain radioactive material, or control nuclear reactivity. For the purposes of this Standard, ESFs are defined as lollows:
(a) maintaining adequate decay heat removal.
(b) maintaining reactor coobnt system and spent fuel pool inventory necessary for adequate shielding, removal of decay heat. and contarnment of radioactive material, This may be accomplished by preventing leakage from the reactor vessel (during refueling) and spent fuel pool in excess of safety-related makeup capability.
(c) preventing damage to Irradiated fuel or to components that Function to prevent a substantial release of radioactivity. As used here, a substantial release of radioactivity means the potential for radiation exposures comparable in magnitude to those specified in 10 C.F.R 4 5O.34(a)(1), 4 50.67(b)(2), or 4100.11.
(d) maintaining the geometric configuration of multiple fuel assemblies such that nuclear reactivity cannot increase.
facility acceptable excursion limit (MEL): the distance a load can move where its movement remains safe. This limit applies to any hoist or travel motion when uncom• manded load movement occurs. It is intended to assume a mechanical or a control system failure has occurred and manual or automatic systems must be used to stop the load.
infrequently performed test and evolution (IPTE): mirequently performed test or evolution that has the potential to significantly degrade the plant’s margin of safety and therefore warrants additional management oversight and control.
intermediate hoist: an additional hoist that is used as part of the rigging below the primary hoist It could be used as a means of leveling the load or as a more precise means of lifting the load.
lift. critical: any lift that carries a high risk of a load-handling event, as determined by the presence of certain p rob- ability factors and the severity of the possible consequences of such an event.
lift. nuclear safety critical: any lift, performed in a given area after a plant becomes operational. In which the load weighs more than the combined weight of a single spent fuel assembly and its associated handling tool for the specific plant in question that, as a result of uncontrolled motion exceeding the movement safety envelope, can result in the loss of an essential safety function. Nuclear safety critical lifts are a subset of critical lifts.ASME NML-1 pdf download.