Document: NUREG-0800
Document ID: 062bafc6-0bc5-4a2f-a566-7200c0c49d7a
Document Type: srp
Title: ENGINEERED SAFETY FEATURES SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B099.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.3
CFR Part: 
CFR Title: 

Content:
cy Core Cooling.” 4. GDC 38, “Containment Heat Removal.” 5. GDC 41, “Containment Atmosphere Cleanup.” 6. GDC 44, “Cooling Water.” SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC’s regulations identified above are contained in SRP Section 7.1, SRP Table 7-1 and SRP Appendix 7.1-A which list standards, RGs, and branch technical positions (BTPs). The SRP is not a substitute for the NRC’s regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical techniques, and procedural measures proposed for its facility and the SRP acceptance criteria and evaluate how the proposed alternatives to the SRP acceptance criteria provide acceptable methods of compliance with the NRC regulations. 1. SRP Appendix 7.1-C provides SRP acceptance criteria for safety system compliance with 10 CFR 50.55a(h). 2. SRP Appendix 7.1-B provides SRP acceptance criteria for protection system compliance with 10 CFR 50.55a(h). 7.3-6 Draft Revision 6 – August 2015 3. IEEE Std 7-4.3.2, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,” as endorsed by RG 1.152, “Criteria for Digital Computers in Safety Systems of Nuclear Power Plants,” provides guidance on applying the safety system criteria to computer-based safety systems. SRP Appendix 7.1-D provides SRP acceptance criteria for safety and protection systems using digital computer-based technology. 4. Item II.Q, “Defense against Common-Mode Failures in Digital Instrument and Control Systems,” of the Staff Requirements Memorandum on SECY-93-087, “Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light Water Reactor (ALWR) Designs,” provides guidance on Diversity and Defense-in-Depth. SRP BTP 7- 19 provides additional guidance. III. REVIEW PROCEDURES The reviewer will select material from