Document: NUREG-0800
Document ID: fe8ec6c2-e960-404c-854f-55c77bde1672
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML2400/ML24005A077.pdf
Revision Date: 2024-05
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
ceptance Criteria, and Guidelines for Instrumentation and Control Systems Important to Safety” (Agencywide Documents Access and Management System Accession No. ML16020A103). 2. NRC, Regulatory Guide (RG) 1.70, Revision 3, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” November 1978 (ML011340122). 3. Institute of Electrical and Electronics Engineers (IEEE) Std 279-1968, “Proposed IEEE Criteria for Nuclear Power Plant Protection Systems,” Piscataway, NJ, August 1968. 4. IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations,” Piscataway, NJ, June 1971. 5. IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” Piscataway, NJ, June 1991. 6. IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” Correction Sheet, Piscataway, NJ, January 30, 1995. 7. NRC, RG 1.233, Revision 0, “Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light-Water Reactors,” June 2020 (ML20091L698). BTP 7-19-39 Revision 9 — May 2024 8. NRC, RG 1.62, Revision 1, “Manual Initiation of Protective Actions,” June 2010 (ML092530559). 9. NRC, RG 1.53, Revision 2, “Application of the Single-Failure Criterion to Safety Systems,” November 2003 (ML033220006). 10. NRC, RG 1.152, Revision 4, “Criteria for Programmable Digital Device in Safety-Related Systems of Nuclear Power Plants,” July 2023 (ML23054A463). 11. NRC, RG 1.174, Revision 3, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis,” January 2018 (ML17317A256). 12. NRC, NUREG-0800, Section 19.0, “Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors,” Revision 3, December 2015