Oct,03

ASME NML-1:2019 pdf download

ASME NML-1:2019 pdf download

ASME NML-1:2019 pdf download.Rules for the Movement of Loads Using Overhead Handling Equipment in Nuclear Facilities
cascading failures: a process in a system ofinterconnected parts in which the failure ofone or a few parts can trigger the failure of other parts and so on. design ratedtorque: thetorque requiredto holdthe design rated load of the hoist at the point of brake application. double-rigging arrangement: a system in which two inde- pendent sets of load-carrying elements, each capable of carryingthe load, are used to connectthe load to the over- head handling equipment. emergencyresponseplan:asetofactionsnecessarytomiti- gate the consequences ofthe worstpossible outcomes ofa load-handling accident. engineered temporary lift assembly (ETLA): 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 fromacommercialsource, andthere is no gener- ally accepted consensus standard applicable to the equip- ment. Examples of ETLAs include special gin poles and derricks; special crane supports such as runways or over- head 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 ofASME B30). ETLAs are required for lifts that cannotbe accomplished with standard lifting devices. essential safety function (ESF): a function performed by a plantsystem, structure, orcomponentthatis necessaryto remove decayheatfrom irradiatedfuel, provide shielding, contain radioactive material, orcontrol nuclearreactivity. For the purposes of this Standard, ESFs are defined as follows: (a) maintaining adequate decay heat removal. (b) maintaining reactor coolant system and spent fuel pool inventory necessary for adequate shielding, removal of decay heat, and containment 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 compo- nents that function to prevent a substantial release of radioactivity. As used here, a substantial release ofradio- activity means the potential for radiation exposures comparable in magnitude to those specified in 10 C.F.R § 50.34(a)(1), § 50.67(b)(2), or § 100.11. (d) maintaining the geometric configuration of multiple fuel assemblies such that nuclear reactivity cannot increase. facility acceptable excursion limit (FAEL): the distance a load can move where its movement remains safe. This limit applies to any hoist or travel motion when uncom- manded load movementoccurs. Itis 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): infre- quentlyperformed testor evolution thathas the potential to significantly degrade the plant’s margin of safety and therefore warrants additional managementoversightand control. intermediate hoist: an additional hoist that is used as part oftheriggingbelowthe primaryhoist. Itcouldbeusedas a means ofleveling the load or as a more precise means of lifting the load. lift, critical: any lift that carries a high risk of a load-han- dlingevent,asdeterminedbythepresenceofcertainprob- 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 assemblyand its associated handling tool for the spe- cific 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. 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 assemblyand its associated handling tool for the spe- cific 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. lift, special: any lift that carries a moderate risk ofa load- handling event, as determined by the presence ofcertain probability factors and the severity ofthe possible conse- quences of such an event.

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