Document: NUREG-0800
Document ID: b9958157-a0b8-4321-b294-effbf265eda5
Document Type: srp
Title: ENGINEERED SAFETY FEATURES SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070560004.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.3
CFR Part: 
CFR Title: 

Content:
y Feedwater System Automatic Initiation and Flow Indication.” (2)(xiv), “Containment Isolation Systems.” 2. GDC 20, “Protection Systems Function.” 3. GDC 21, “Protection System Reliability and Testability.” 7.3-5 Revision 5 - March 2007 4. GDC 22, “Protective System Independence.” 5. GDC 23, “Protection System Failure Modes.” 6. GDC 24, “Separation of Protection and Control Systems.” 7. GDC 29, “Protection against Anticipated Operational Occurrences.” Additional acceptance criteria applicable to ESF control systems 1. GDC 33, “Reactor Coolant Makeup.” 2. GDC 34, “Residual Heat Removal.” 3. GDC 35, “Emergency 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, regulatory guides, 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). 3. IEEE Std 7-4.3.2-2003, “IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations,” as endorsed by Regulatory Guide 1.152, Revision 2, “Criteria for Digital Computers in Safety Systems of Nuclear Power