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Implementation of Containment-Related GDC

GDC 1 Quality Standards and Records

“Quality standards and records: Structures, systems, and components important to safety shall be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Where generally recognized codes and standards are used, they shall be identified and evaluated to determine their applicability, adequacy, and sufficiency and shall be supplemented or modified as necessary to assure a quality product in keeping with the required safety function. A quality assurance program shall be established and implemented in order to provide adequate assurance that these structures, systems, and components will satisfactorily perform their safety functions. Appropriate records of the design, fabrication, erection, and testing of structures, systems, and components important to safety shall be maintained by or under the control of the nuclear power unit licensee throughout the life of the unit.”

This is a general criterion applicable to all safety-related structures, systems, and components. ASME NQA-1 (2008) [11], and NQA-1a (2009) [12] QA requirements are applicable to the extent they are endorsed by NRC in RG 1.28 (2010) [13]. Generally recognized Code for design, construction, and testing of steel containments is Subsection NE [4] of Section III, Division 1 of the Boiler and Pressure Vessel (B & PV) Code of the American Society of Mechanical Engineers (ASME), as endorsed by RG 1.57 [5]. Generally recognized Code for concrete containments is Subsection CC [15] of Section III, Division 2 of the ASME B & PV Code, as endorsed by RG 1.136 (2007) [16]. The general requirements for structures and components of both the divisions are specified in Subsection NCA [17] of Section III of the ASME B & PV Code.

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