Document: NUREG-0800
Document ID: b3d7a8f7-62f4-4ace-b8c7-32606edaa8f5
Document Type: srp
Title: CONTROL SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B161.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.7
CFR Part: 
CFR Title: 

Content:
IEEE Std 603-1991, Clause 6.3, “Interaction Between the Sense and Command Features and Other Systems.” 7.7-4 Draft Revision 6 – August 2015 3. 10 CFR 50.34(f)(2)(xxii), “Additional TMI-Related Requirements,” (applies only to B&W plants) or equivalent Three Mile Island Action Plan requirements imposed by Commission order. 4. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “General Design Criteria for Nuclear Power Plants,” Design Criterion (GDC) 1, “Quality Standards and Records.” 5. GDC 10, “Reactor Design.” 6. GDC 13, “Instrumentation and Control.” 7. GDC 15, “Reactor Coolant System Design.” 8. GDC 19, “Control Room.” 9. GDC 24, “Separation of Protection and Control Systems.” 10. GDC 28, “Reactivity Limits.” 11. GDC 29, “Protection against Anticipated Operational Occurrences.” 12. GDC 44, “Cooling Water.” 13. 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 accordance with the design certification, the provisions of the Atomic Energy Act, and the U.S. Nuclear Regulatory Commission’s (NRC’s) regulations. 14. 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. SRP Acceptance Criteria Specific SRP acceptance criteria