Document: NUREG-0800
Document ID: 5691df7d-390d-4ce8-953e-bbdb0a812705
Document Type: srp
Title: REACTOR TRIP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B086.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
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of applications that the staff may review. Refer to that section for information regarding how the areas of review are affected by the type of application under consideration and for a description of coordination between the organization responsible for the review of instrumentation and control systems and other organizations. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. 7.2-3 Draft Revision 6 – August 2015 II. ACCEPTANCE CRITERIA Requirements Acceptance criteria for the review of the RTS are based on meeting the relevant requirements of the following Commission regulations: 1. Title 10 of the Code of Federal Regulations (10 CFR) 50.54(jj) and 10 CFR 50.55(i). 2. Regulations in 10 CFR 50.55a(h), “Protection and Safety Systems,” require compliance with the Institute of Electrical and Electronics Engineers (IEEE) Standard (Std) 603- 1991, “IEEE Standard 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, 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 50.34(f), “Additional TMI-Related Requirements,” or equivalent TMI action requirements imposed by Generic Letters. 10 CFR 50.34(f)(2)(v), “Bypass and Inoperable Status Indication.” 10 CFR 50.34(f)(2)(xxiii), “Anticipatory Trip on Loss of Main Feedwater or Turbine Trip.” 4. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion (GDC) 1,