Document: NUREG-0800
Document ID: 6209b3e7-917d-48d2-a299-4d1230aa5b51
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550070.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
nstead 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 50 Appendix A, 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 possible or (2) detected and suppressed. This requirement places strict real-time constraints on any protection system components that detect and suppress power oscillations. GDC 13, "Instrumentation and Control," requires in part that instrumentation be provided to monitor variables and systems over their anticipated ranges for normal operations, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety. Digital instrumentation must respond quickly enough so that the behavior of variables can be ascertained by operators. GDC 19, "Control Room," requires in part that applicants establish a control room from which actions can be taken to operate the nuclear power unit safely under normal conditions, and to maintain the nuclear power unit in a safe condition during an accident. In addition, a remote shutdown capability is required to permit the reactor to be safely shut down. GDC 20, "Protection System Functions," requires in part that the reactor