Document: NUREG-0800
Document ID: 2cd63ebf-9196-42c0-880d-a80500b202a4
Document Type: srp
Title: - 15.1.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550005.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.1
CFR Part: 
CFR Title: 

Content:
n Criterion 13, Instrumentation and Control.” 7. 10 CFR Part 50, Appendix A, General Design Criterion 15, "Reactor Coolant System Design." 8. 10 CFR Part 50, Appendix A, General Design Criterion 20, "Protection System Functions." 9. 10 CFR Part 50, Appendix A, General Design Criterion 26, "Reactivity Control System Redundancy and Capability." 10. Regulatory Guide 1.53, "Application of the Single Failure Criterion to Nuclear Power Plant Systems Protection." 11. Regulatory Guide 1.105, "Instrument Spans and Setpoints." 12. NUREG-0737, "Clarification of TMI Action Plan Requirements." 13. NRC Memorandum dated March 15, 1983, Mattson to Dircks, "Closeout of NUREG-0660 Item II.E.5.1 Design Sensitivity of B&W Plants for Operating Plants." 14. NRC Memorandum dated September 28, 1984, Denton to Dircks, "Closeout of TMI Action Plan Task II.E.5.2, Transient Response of B&W-Designed Reactors." 15. NUREG-0793, Midland Safety Evaluation Report and Supplement 1, Section 5.5, "Design Sensitivity of B&W Reactors." PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50 and 10 CFR Part 52, and were approved by the Office of Management and Budget, approval number 3150-0011 and 3150-0151. PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number. 15.1.1-15.1.4-12 Revision 2 - March 2007