Document: NUREG-0800
Document ID: 949ca18d-b0e4-4b54-9ca9-fdb657988111
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070660170.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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strictions (e.g., interface requirements and site parameters) included in the referenced DC. Appendix 7.1-A-3 Revision 5 - March 2007 1. Regulations - 10 CFR Part 50 (a) 10 CFR 50.55a(a)(1): Addresses Quality Standards for Systems Important to Safety "Structures, systems, and components must be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed." Applicability - All I&C systems Review Methods - The applicant/licensee should commit to conformance with the regulatory guides and standards referenced in SRP Sections 7.1 through 7.9 and the BTPs in SRP Appendix 7-A. The design should conform to all regulatory guides and standards committed to by the applicant/licensee. (b) 10 CFR 50.55a(h)(2), "Protection Systems" "For nuclear power plants with construction permits issued after January 1, 1971, but before May 13, 1999, protection systems must meet the requirements stated in either IEEE Std. 279-1971, ‘Criteria for Protection Systems for Nuclear Power Generating Stations,' or IEEE Std. 603-1991, ‘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, protection systems must be consistent with their licensing basis or may meet the requirements of IEEE Std. 603-1991 and the correction sheet dated January 30, 1995." Applicability - The protection systems: reactor trip system (RTS), engineered safety features actuation system (ESFAS), auxiliary supporting features and other supporting features, and supporting data communication systems. One part of each IEEE standard also applies to all I&C systems, and one part of each standard applies to information systems important to safety. The parts applicable to all I&C systems are: • IEEE Std. 603-1991, Clause 5.6.3, "Independence Between Safety Systems and Other Systems," and •