Document: NUREG-0800
Document ID: 757b676a-0f71-4094-8677-ca3a50743281
Document Type: srp
Title: Revision 7 – August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A344.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
ction.” 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 safety functions.” 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” governs the issuance of early site permits (ESPs), 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, “Accident Source Term.” BTP 7-19-4 Revision 7 – August 2016 These guideline values can be commonly referred to as the site dose guideline values: ● 10 CFR 50.67 provides guideline values for fission product releases from currently operating NPPs that have implemented an alternative source term. ● 10 CFR 50.34(a)(1)(ii)(D) provides guideline values for CP applicants and NPPs licensed to operate under Part 50 after January 10, 1997. ● 10 CFR 52.47(a)(2)(iv) provides guideline values for standard DCs. ● 10 CFR 52.79(a)(1)(vi) provides guideline values for COLs. ● 10 CFR 52.137(a)(2)(iv) provides guideline values for SDAs. ● 10 CFR 52.157(d) provides guideline values for ML approvals. 2. Relevant Guidance RG 1.53, “Application of the Single-Failure Criterion to Safety Systems,” clarifies the application of the single-failure criterion (GDC 21) and endorses IEEE Std 379, “IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems,”