Document: NUREG-0800
Document ID: 1df526d9-2ae0-4da2-b936-2e24b038ca8c
Document Type: srp
Title: DIVERSE INSTRUMENTATION AND CONTROL SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070650035.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.8
CFR Part: 
CFR Title: 

Content:
- March 2007 4. GDC 13, “Instrumentation and Control.” 5. GDC 19, “Control Room.” 6. GDC 24, “Separation of Protection and Control Systems.” Note that the design of the diverse I&C systems must be such that the protection system continues to meet the requirements of 10 CFR 50, Appendix A, “General Design Criteria for Nuclear Power Plants,” Section III, “Protection and Reactivity Control Systems.” Review of the reactor protection system for these areas of conformance is addressed in SRP Sections 7.2 and 7.3. Additional requirements applicable to any information system important to safety proposed for standard DC or COLs under 10 CFR 52 7. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed inspections, tests, analyses, and acceptance criteria (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 accordance with the design certification, the provisions of the Atomic Energy Act, and the NRC's regulations; 8. 10 CFR 52.80(a), which requires that a COL application contain the proposed inspections, tests, and analyses, including those applicable to emergency planning, that the licensee shall perform, and the acceptance criteria that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, the facility has been constructed and will operate in conformity with the combined license, the provisions of the Atomic Energy Act, and the NRC's regulations. Additional acceptance criteria applicable to ATWS mitigation functions: 9. 10 CFR 50.62, “Requirements for reduction of risk from ATWS events for light-water-cooled nuclear power plants.” SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the