Document: NUREG-0800
Document ID: 899b3059-69f1-4f7b-bead-1d58e5f4870f
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550080.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
in this BTP. Refer to SRP Appendix 7.1-C subsection 5.6 and SRP Appendix 7.1-D subsection 5.6. 1. Regulatory Basis 10 CFR 50.55a(h), “Protection and Safety Systems,” requires compliance with IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” and the correction sheet dated January 30, 1995. For nuclear power plants with construction permits issued before January 1, 1971, the applicant/licensee may elect to comply instead with the plant-specific licensing basis. For nuclear power plants with construction permits issued between January 1, 1971, and May 13, 1999, the applicant/licensee may elect to comply instead with the requirements stated in IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” IEEE Std 603-1991, Clause 5.6, “Independence,” states in part, “No credible failure on the non-safety side of an isolation device shall prevent any portion of a safety system from meeting its minimum performance requirements during and following any design basis event requiring that safety function.” IEEE Std 279-1971, Clause 4.7.2, “Isolation Devices,” states in part, “No credible failure at the output of an isolation device shall prevent the associated protection system channel from meeting the minimum performance requirements specified in the design basis. 10 CFR Part 50 Appendix A, General Design Criterion (GDC) 1, “Quality Standards and Records,” requires in part that “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.” GDC 1 also requires that “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