Document: NUREG-0800
Document ID: dc63e8aa-2a74-4078-9e19-9a26ed1b4d8c
Document Type: srp
Title: Revision 6 – July 2012
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1105/ML110550791.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
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 NPPs with construction permits (CPs) issued before January 1, 1971, the applicant may elect to comply instead with its plant-specific licensing basis. For NPPs with CPs issued between January 1, 1971, and May 13, 1999, the applicant 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 5.1, requires in part that “safety systems shall perform all safety functions required for a design basis event (DBE) in the presence of: any single detectable failure within the safety systems concurrent with all identifiable, but non-detectable failures.” IEEE Std. 603-1991, Clause 6.2, “Manual Control,” requires in part that a means shall be provided in the control room to implement manual initiation at the division level of the automatically initiated protective actions. IEEE Std. 603-1991, Clause 7.2, “Manual Control,” requires in part that the means of any manual control of any execute features shall not defeat requirements of Clauses 5.1 and 6.2. IEEE Std. 279-1971, Clause 4.2, requires in part that “any single failure within the protection Revision 6 – July 2012 BTP 7-19-3 system shall not prevent proper protective action at the system level when required.” IEEE Std. 279-1971, Clause 4.17, “Manual Initiation,” requires in part that the protection system shall include means for manual initiation of each protective action at the system level. 10 CFR 50.62, “Requirements for Reduction of Risk from Anticipated Transients without Scram (ATWS) Events for Light-water-cooled Nuclear Power Plants,” requires in part various diverse methods of responding to ATWS. 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 21, “Protection