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ASME BPVC XI-2-2021
Condition: New
Format: PDF Digital
Published: 07/01/2021
ISBN: 9780791874295
Publisher: ASME
Provides requirements to maintain the nuclear power plant while in operation and to return the plant to service following plant outages. The rules require a mandatory program to evidence adequate safety and manage deterioration and aging effects. The rules also stipulate duties of the Authorized Nuclear Inservice Inspector to verify that the mandatory program has been completed, permitting the plant to return to service in a safe and expeditious manner. Application of this Section begins when the requirements of the construction code have been satisfied.
DIVISION 2
This Division provides the requirements for the creation of the Reliability and Integrity Management (RIM) Program for advanced nuclear reactor designs. The RIM Program addresses the entire life cycle for all types of nuclear power plants, it requires a combination of monitoring, examination, tests, operation, and maintenance requirements that ensures each Structure, System, and Component (SSC) meets plant risk and reliability goals that are selected for the RIM Program.
Published:
07/01/2021
ISBN(s):
9780791874295
Number of Pages:
151
Product Code(s):
300112, 300112
ASME BPVC 2019 Series contains the following:
ASME BPVC Code Cases: Nuclear Components
ASME BPVC Section I-Rules for Construction of Power Boilers
ASME BPVC Section II-Materials-Part A-Ferrous Materials Specifications (2 Volumes)
ASME BPVC Section II-Materials-Part B-Nonferrous Material Specifications
ASME BPVC Section II-Materials Part C-Specifications for Welding Rods Electrodes and Filler Metals
ASME BPVC Section II-Materials-Part D-Properties-(Customary)
ASME BPVC Section II-Materials-Part D-Properties-(Metric)
ASME BPVC Section III-Rules for Construction of Nuclear Facility Components-Division 1-Subsection NB-Class 1 Components
ASME BPVC Section III: Rules for Construction of Nuclear Power Plant Components, Subsection NCA: General Requirements for Division 1 and Division 2
ASME BPVC Section III-Rules for Construction of Nuclear Facility Components-Division 1-Subsection NE-Class MC Components
ASME BPVC Section III-Rules for Construction of Nuclear Facility Components-Division 1-Subsection NF-Supports
ASME BPVC Section III-Rules for Construction of Nuclear Facility Components-Division 1-Subsection NG-Core Support Structures
ASME BPVC Section III-Rules for Construction of Nuclear Power Plant Components, Division 2: Code for Concrete Reactor Vessels and Containments
ASME BPVC Section III-Rules for Construction of Nuclear Facility Components-Division 3-Containments for Transportation & Storage of Spent Nuclear Fuel & High Level Radioactive Material & Waste
ASME BPVC Section III-Rules for Construction of Nuclear Facility Components-Division 5-High Temperature Reactors
ASME BPVC Section III-Rules for Construction of Nuclear Facility Components-Division 1-Appendices
ASME BPVC Section III-Rules for Constructions of Nuclear Facility Components-Subsection NCA-General Requirements for Division 1 and Division 2
ASME BPVC Section IV-Rules for Construction of Heating Boilers
ASME BPVC Section IX-Welding, Brazing, and Fusing Qualifications
ASME BPVC Section V-Nondestructive Examination
ASME BPVC Section VI-Recommended Rules for the Care and Operation of Heating Boilers
ASME BPVC Section VII-Recommended Guidelines for the Care of Power Boilers
ASME BPVC Section VIII-Rules for Construction of Pressure Vessels Division 1
ASME BPVC Section VIII-Rules for Construction of Pressure Vessels Division 2-Alternative Rules
ASME BPVC Section VIII-Rules for Construction of Pressure Vessels Division 3-Alternative Rules for Construction of High Pressure Vessels
ASME BPVC Section X-Fiber-Reinforced Plastic Pressure Vessels
ASME BPVC Section XI-Rules for Inservice Inspection of Nuclear Power Plant Components
ASME BPVC Section XII-Rules for Construction and Continued Service of Transport Tanks
ASME Boiler and Pressure Vessel Code, Section XIII, Rules for Overpressure Protection