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:
rnative 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 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. Revision 6 – July 2012 BTP 7-19-4 ● 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 Regulatory Guide (RG) 1.53, Revision 2, “Application of the Single-Failure Criterion to Safety Systems,” clarifies the application of the single-failure criterion (GDC 21) and endorses IEEE Std. 379-2000, “IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems,” providing supplements and an interpretation. IEEE Std. 379-2000, Clause 5.5, establishes the relationship between CCF and single failures by defining criteria for CCF’s that are not subject to single-failure analysis. This clause also identifies D3 as a technique for addressing CCF. RG 1.152, Revision 3, “Criteria for Use of Computers in Safety Systems of Nuclear Power Plants,” which endorses IEEE Std. 7-4.3.2-2003, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,” with a few noted exceptions, provides guidance for complying with requirements for safety systems that use digital computers. Additional guidance on the application of IEEE Std. 7-4.3.2 is provided in Standard Review Plan (SRP), Chapter 7, Appendix 7.1-D. RG 1.62, Revision 1, “Manual Initiation of Protective Actions,” includes information on diverse manual initiation of