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:
TWS) 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 System Reliability and Testability,” requires in part that “Redundancy and independence designed into the protection system shall be sufficient to assure that (1) no single failure results in the loss of the protection function.” GDC 22, “Protection System Independence,” requires in part “that the effects of natural phenomena, and of normal operating, maintenance, testing, and postulated accident conditions on redundant channels do not result in loss of the protection function Y Design techniques, such as functional diversity or diversity in component design and principles of operation, shall be used to the extent practical to prevent loss of the protection function.” GDC 24, “Separation of Protection and Control Systems,” requires in part that “interconnection of the protection and control systems shall be limited so as to assure that safety is not significantly impaired.” GDC 29, “Protection Against Anticipated Operational Occurrences,” requires, in part, defense against anticipated operational transients “to assure an extremely high probability of accomplishing Y safety functions.” 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” governs the issuance of early site permits, standard DCs, combined licenses (COLs), standard design approvals (SDAs), and manufacturing licenses (MLs) for nuclear power facilities. 10 CFR Part 100, “Reactor Site Criteria,” provides guideline values for fission product releases from NPPs licensed to operate prior to January 10, 1997 that have voluntarily implemented an alternative source term under the provisions of 10 CFR 50.67. These guideline values can be commonly referred to as the siting dose guideline values: ● 10 CFR 50.67 provides guideline values for fission