Document: NUREG-0800
Document ID: 062bafc6-0bc5-4a2f-a566-7200c0c49d7a
Document Type: srp
Title: ENGINEERED SAFETY FEATURES SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B099.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.3
CFR Part: 
CFR Title: 

Content:
e contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 7.3-4 Draft Revision 6 – August 2015 Acceptance criteria applicable to any ESFAS and ESF control systems: 1. Title 10 of the Code of Federal Regulations (10 CFR) 50.54(jj) and 10 CFR 50.55(i). 2. 10 CFR 50.55a(h), “Protection and Safety Systems,” which requires compliance with IEEE Std 603-1991,” and the correction sheet dated January 30, 1995. For 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 comply instead with the requirements stated in IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” 3. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “General Design Criteria for Nuclear Plants” General Design Criterion (GDC) 1, “Quality Standards and Records.” 4. GDC 2, “Design Basis for Protection against Natural Phenomena.” 5. GDC 4, “Environmental and Dynamic Effects Missile Design Basis.” 6. GDC 10, “Reactor Design.” 7. GDC 13, “Instrumentation and Control.” 8. GDC 15, “Reactor Coolant System Design.” 9. GDC 16, “Containment Design.” 10. GDC 19, “Control Room.” 11. 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