Inservice inspection

XI. Rules for Inservice Inspection of Nuclear Power Plant Components... [Pg.1022]

Rules for inservice inspection of nuclear power plant components... [Pg.178]

NRC Regulatory Guide 1,47, "Inservice Inspection Code Case Acceptability ASME Section XI Division 1."... [Pg.26]

Section XI provides requirements for the preservice and periodic inservice inspections pump, valve and snubber tests pressure tests and for the repair and replacement of pressure retaining components, including their integral attachments and component supports, classified as ASME Class 1, 2, and 3. [Pg.67]

Inservice inspections, tests, and repairs and replacements conducted during the ten year inspection intervals should comply with the latest edition and addenda of the Code referenced in this implementation guidance 12 months prior to the start of the next inspection interval. Later editions and addenda of the Code that are incorporated by reference into this paragraph may be used subject to any I imitations and modifications noted in this implementation guidance. [Pg.67]

PRACTICAL EXPERIENCE GAINED ON INSERVICE INSPECTIONS OF PWR PRESSURE VESSELS... [Pg.33]

Other appropriate requirements to minimize the probability or consequences of an accidental rupture of these lines or of lines connected to them shall be provided as necessary to assure adequate safety. Determination of the appropriateness of these requirements, such as higher quality in design, fabrication, and testing, additional provisions for inservice inspection, protection against more severe natural phenomena, and additional isolation valves and containment, shall include consideration of the population density, use characteristics, and physical characteristics of the site environs. [Pg.352]

Reactor Coolant Pressure Boundary Inservice Inspection and Testing... [Pg.398]

A task force has reviewed the Inservice Inspection requirement of NSS systems/ components and recommendations have been made for I SI. [Pg.93]

ASME (2010b), ASME Boiler and Pressure Vessel Code, Section XI, Inservice inspection of nuclear power plant components, American Society of Mechanical Engineers, New York. [Pg.24]

The reactor coolant pump pressure boundary is nondestructively inspected as required by ASME Section III for Class 1 components. The pump casing inspections include complete radiography and liquid penetrant or ultrasonic testing. The pump receives a hydrostatic pressure test in the vendor s shop and with the Reactor Coolant System. Inservice inspection of the pump pressure boundary will be performed during plant life in accordance with ASME Section XI. [Pg.135]

Inservice inspection of the steam generator is described in Section 5.2.4. [Pg.146]

Further assurance of the structural integrity of the pressurizer during plant life will be obtained from the inservice inspections performed in accordance with ASME Code, Section XI, and described in Section 5.2. [Pg.194]

INSERVICE INSPECTION CRITERIA FOR SUPPORT OF CLASS 1, 2, AND 3 AND MC COMPONENTS... [Pg.43]

INSERVICE INSPECTION CRITERIA AND CORROSION PREVENTION CRITERIA FOR CONTAINMENTS... [Pg.43]

The acceptance criteria for the resolution of GSI 029 are that proven bolting designs, materials, and fabrication techniques shall be employed. In addition, reactor coolant pressure boundary (RCPB) bolting shall meet the requirements of ASME Code, Section III (Reference 2). Also, for RCPB bolting the owner-operator shall use established industry practice in developing maintenance, assembly, and disassembly procedures. Furthermore for RCPB and its support bolting, inservice inspection shall meet the requirements of ASME, Section XI (Reference 2),... [Pg.114]

In summary, the bolting for RCPB components and supports are selected considering their particular application and are fabricated, tested and installed in accordance with ASME Sections III. Furthermore, the owner-operator is required to comply with ASME Code, Section XI for the performance of inservice inspection. Therefore, this issue is resolved for the System 80+ Standard Design. [Pg.115]

Accessibility of containment spray system and sump(s) for inservice inspection. [Pg.249]

The characterization of the steel and weel materials was established through industrial and governmental studies which examined the material properties in both the unirradiated and the irradiated condition. Inservice inspection and material surveillance programs are also conducted during the service life of the vessel, further ensuring adequate vessel integrity and safety margin. [Pg.263]

Regulatory Guide 1.178 and Standard Review Plan Section 3.9.6 Inservice inspection (ISI)... [Pg.647]

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