Document: NUREG-0800
Document ID: 6acfc377-3e1c-4cb9-b2d1-500f564d2f4b
Document Type: srp
Title: Draft Revision 6 – August 2015
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B011.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
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Content:
UREG/CR-6083, “Reviewing Real-Time Performance of Nuclear Reactor Safety Systems,” and NUREG/CR-6082, “Data Communications.” 1. Regulatory Basis Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(h), “Protection and Safety Systems,” requires compliance with the requirements of 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 4.10, requires in part that safety system design bases document the critical points in time or plant conditions after the onset of a design-basis event. This information establishes requirements for system response times. IEEE Std 603-1991, Clause 5.5, requires in part that safety systems be designed to accomplish their safety functions under the full range of applicable conditions enumerated in the design basis. 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) 10, “Reactor Design,” requires in part that control and protection systems be designed with appropriate margin to assure that specified acceptable fuel damage limits are not exceeded. This includes timing and performance margins. GDC 12, “Suppression of Reactor Power Oscillations,” requires in part that reactor power oscillations are either (1) not