Document: NUREG-0800
Document ID: a8dee0cd-6529-4ac9-b659-26bda40aba48
Document Type: srp
Title: INFORMATION SYSTEMS IMPORTANT TO SAFETY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B138.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.5
CFR Part: 
CFR Title: 

Content:
e and Command Features and Other Systems.” 17. GDC 1, “Quality Standards and Records.” 18. GDC 13, “Instrumentation and Control.” 19. GDC 19, “Control Room.” 20. GDC 24, “Separation of Protection and Control Systems.” Requirements applicable to the review of SPDS, ERF information systems, and ERDS information systems 21. 10 CFR 50.54(jj) and 10 CFR 50.55(i)” 22. 10 CFR 50.55a(h), requires compliance with IEEE Std 603-1991 and the correction sheet dated January 30, 1995. Nuclear power plants with construction permits issued before January 1, 1971, the applicant or licensee may elect to comply instead with their plant-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 7.5-6 Draft Revision 6 – August 2015 comply instead with the requirements stated in IEEE Std 279-1971. For SPDS, ERF information systems, and ERDS information systems isolated from the protection system, the applicable requirements of 10 CFR 50.55a(h) for IEEE Std 279-1971 is Clause 4.7, “Control and Protection System Interaction,” and for IEEE Std 603-1991 are Clause 5.6.3, “Independence Between Safety Systems and Other Systems,” and Clause 6.3, “Interaction Between the Sense and Command Features and Other Systems.” 23. GDC 1, “Quality Standards and Records.” 24. GDC 24, “Separation of Protection and Control Systems.” Additional requirements applicable to any information system important to safety proposed for standard DC or COLs under 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants.” 25. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed ITAAC that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the design certification is built and will operate in