Document: NUREG-0800
Document ID: fea61ff0-f344-4101-adfb-590e3d9dfafe
Document Type: srp
Title: Draft Revision 6 – August 2015
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A946.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
specific licensing basis. For nuclear power plants with construction permits issued between January 1, 1971 and May 13, 1999 the applicant or licensee may elect to comply instead with the requirements stated in IEEE Std 279- 1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” Clause 4.3 of IEEE Std 279-1971 states in part that quality of components is to be achieved through the specification of requirements known to promote high quality, such as requirements for design, inspection, and test. Similar criteria for the quality of components are identified in IEEE Std 603-1991. Additional guidance on the application of IEEE Std 279-1971 is provided in SRP Appendix 7.1-B. Additional guidance on the application of IEEE Std 603-1991 is provided in SRP Appendix 7.1-C. 3. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion (GDC) 1, “Quality Standards and Records,” requires in part that systems and components important to safety 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 should be identified and evaluated to determine their applicability, adequacy, and sufficiency, and should be BTP 7.14-3 Draft Revision 6 - August 2015 supplemented or modified as necessary to ensure a quality product consistent with the required safety function. 4. GDC 21, “Protection System Reliability and Testability,” requires in part that protection systems be designed for high functional reliability commensurate with the safety function to be performed. 5. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” Criterion III, “Design Control,” requires in part that quality standards be specified and that design control