Search
  • uesuae

NUCLEAR INSERVICE

SECTION XI RULES FOR INSERVICE INSPECTION OF NUCLEAR POWER PLANT COMPONENTS

Provides rules for the examination, inservice testing and inspection, and repair and replacement of components and systems in light water-cooled nuclear power plants. Application of Section XI begins when the requirements of the “construction code” (e.g., Section III) have been satisfied.

Section XI constitutes requirements to maintain the nuclear power plant while in operation and to return the plant to service, following plant outages, and repair or replacement activities. These rules require a mandatory program of scheduled examinations, testing, and inspections to evidence adequate safety. The method of nondestructive examination to be used and flaw size characterization are also contained within this Section.


REFERENCED BPVC SECTIONS


BPVC-II, A, B, C, D

Section II, Materials, Parts A through D.


BPVC-III

Section III, Rules for Construction of Nuclear Facility Components:

Subsection NCA, General Requirements for Division 1 and Division 2.

Subsection NB, Class 1 Components.

Subsection NC, Class 2 Component.

Subsection ND, Class 3 Components.

Subsection NE, Class MC Components.

Subsection NF, Supports.

Subsection NG, Core Support Structures.

Appendices.

Division 2-Code for Concrete Containments.

Division 3-Containments for Transportation & Storage of Spent Nuclear Fuel and High-Level Radioactive Material & Waste.

Division 5, High-Temperature Reactors.


BPVC-V

Section V, Nondestructive Examination.


BPVC-VIII-1-2

Section VIII, Pressure Vessels, Division 1 and Division 2.


BPVC-IX

Section IX, Welding, Brazing, and Fusing Qualifications.


REFERENCED ASME STANDARDS


NQA-1

Quality Assurance Requirements for Nuclear Facilities Applications (QA).


QAI-1

Qualifications for Authorized Inspection.


RA-S

Standard for Level 1 / Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications.


NQA-1

Quality Assurance Requirements for Nuclear Facility Applications (QA).

Provides requirements and guidelines for the establishment and execution of quality assurance programs during siting, design, construction, operation, and decommissioning of nuclear facilities. This Standard reflects industry experience and current understanding of the quality assurance requirements necessary to achieve safe, reliable, and efficient utilization of nuclear energy and management and processing of radioactive materials.


NQA-1 focuses on the achievement of results and emphasizes the role of the individual and line management in the achievement of quality. It fosters the application of these requirements in a manner consistent with the relative importance of the item or activity.


Universal Engineering Services has more than a decades experience in the pressure vessel design for clients in UAE, Oman, Qatar, Kuwait, Bahrain, Saudi Arabia, and many more countries all over the world. UES work to many ASME standards to design and validate pressure vessels, boiler, fittings and piping systems. We are also experts in Stress analysis of piping, structural design, ASME Joint review, Design of Storage tanks, code calculations, FEA/FEM, and spotless service on design management.


**The content of this article is taken from web open source. The blogs are intended only to give technical knowledge to young engineers. Any engineering calculators, technical equations, and write-ups are only for reference and educational purposes.

1 view0 comments

Recent Posts

See All