Document: NUREG-0800
Document ID: 1b840382-003a-4162-a666-f8ba076b669c
Document Type: srp
Title: Revision 6 – August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A316.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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Content:
ines are based on reviews of applicant or licensee submittals and vendor topical submittals describing self-test and surveillance test assumptions, terminology, methodology, and experience gained from U.S. Nuclear Regulatory Commission (NRC) inspections of operating plants. 1. Regulatory Basis Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(h), “Protection and Safety Systems,” requires 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 the 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.” IEEE Std 603-1991, Clause 5.7, requires that capability for testing and calibration of safety system equipment be provided while retaining the capability of the safety systems to accomplish their safety functions. IEEE Std 603-1991, Clause 5.1, requires that the safety system be able to perform its safety function required for a design basis event in the presence of: (1) any single detectable failure within the safety systems concurrent with all identifiable, but non-detectable, failures, (2) all failures caused by the single failure, and (3) all failures and spurious system actions that cause or are caused by the design basis event requiring the safety functions. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” General Design Criterion (GDC) 21,