Home>ASME standards>ASME OM-2012 pdf download

ASME OM-2012 pdf download

ASME OM-2012 pdf download.Operation and Maintenance of Nuclear Power Plants.
ISTA-1400 Referenced Standards and Specifications When standards and specifications are referenced in Section IST, their revision date or indicator shall be as shown in Table ISTA-1400-1. ISTA-1500 Owner’s Responsibilities The responsibilities ofthe Owner ofthe nuclear power plant shall include the following: (a) determination of the appropriate Code Class for each component ofthe plant, identification ofthe system boundaries for each class of components subject to test or examination, and the components exempt from test- ing or examination requirements. (b) design and arrangement of system components to include allowance for adequate access and clearances for conduct of the tests and examinations. Refer to Nonmandatory Appendix M of this Division for guidance. (c) preparation of plans and schedules. (d) preparation of written test and examination instructions and procedures. (e) qualification ofpersonnel who perform and evalu- ate examinations and tests in accordance with the Owner’s quality assurance program. (f) performance of required tests and examinations. (g) recording of required test and examination results that provide a basis for evaluation and facilitate compar- isonwiththe results ofsubsequenttests orexaminations. (h) evaluation of tests and examination results. (i) maintenance ofadequate test and examination rec- ords such as test and examination data and description of procedures used. (j) retention of all test and examination records for the service lifetime of the component or system. (k) documentation of a quality assurance program in accordance with either of the following: (1) Title 10, Code of Federal Regulations, Part 50 (2) ASME NQA-1, Parts II and III ISTA-1600 Accessibility Provisions for examination shall include access for the examination personnel and equipment necessary to conduct the test or examination. ISTA-2000 DEFINITIONS equipment dynamic restraint (snubber): device that pro- vides restraint to a component or system during the sudden application of forces, but allows essentially free motion during thermal movement. examination: observing, visual monitoring, or measuring to determine conformance to Owner-specified requirements. exercising: demonstration based on direct visual or indi- rect positive indications that the moving parts of a com- ponent function. inservice test: test to assess the operational readiness of a system, structure, or component after first electrical generation by nuclear heat. instrument loop: two or more instruments or components working together to provide a single output. instrument loop accuracy: accuracy of an instrument loop based on the square root of the sum of the squares of the inaccuracies of each instrument or component in the loop when considered separately. Alternatively, the allowable inaccuracy of the instrument loop may be based on the output for a known input into the instru- ment loop. maintenance: replacement ofparts, adjustments, and sim- ilar actions that do not change the design (configuration and material) of an item. modification: alteration in the design of a system, struc- ture, or component. monitoring: continuous or periodic observation or mea- surement to ascertain the performance or obtain charac- teristics of a system, structure, or component. nonintrusive testing: testing performed on a component without disassembly or disturbing the boundary of the component. obturator: valve closure member (disk, gate, plug, etc.). operational readiness: the ability of a component to per- form its specified functions. overpressure protection: the means by which components are protected from overpressure by the use of pressure- relieving devices or other design provisions as required by the BPV Code, Section III, or other applicable con- struction codes. Owner: an organization owning or operating a facility where items are installed or used. 7 performance testing: a test to determine whether a system or component meets specified acceptance criteria. plant operation: the conditions of startup, operation at power, hot standby, and reactor cooldown, as defined by plant technical specifications. post-2000 plant: a nuclear power plant that was issued (or will be issued) its construction permit, or combined license for construction and operation, by the applicable regulatory authority on or following January 1, 2000. pre-2000 plant: a nuclear power plant that was issued its construction permit, or combined license for construc- tion and operation, by the applicable regulatory author- ity prior to January 1, 2000. preservice test: test performed after completion of con- struction activities related to the component and before first electrical generation by nuclear heat, or in an operating plant, before the component is initially placed in service. preservicetestperiod: the period oftime followingcomple- tion of construction activities related to the component and before first electrical generation by nuclear heat, in which component and system testing takes place, or in an operating plant prior to the component being initially placed in service. pump: a mechanical device used to move fluid. qualitativetesting: testingperformed to establishparame- ters without determining the specific measure of the parameter. quantitative testing: testing performed to establish the specific measure or limit of a parameter, such as that required to establish that a parameter is within a speci- fied range. reference point: a point of operation at which reference values are established and inservice test parameters are measured for comparison with applicable acceptance criteria. reference values: one or more values of parameters as measured or determined when the equipment is known to be operating acceptably. repair: the process of restoring a degraded item to its original design requirements. routine servicing: performance of planned, preventive maintenance.

Related PowerPoint Templates

Template Categories
Popular Tags