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:
gs will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. 15.1.1-15.1.4-11 Revision 2 - March 2007 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and NUREGS. VI. REFERENCES 1. Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants and Regulatory Guide 1.206, “Combined License Applications for Nuclear Power Plants (LWR Edition)." 2. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components." Article NB-7000, "Protection against Overpressure," American Society of Mechanical Engineers. 3. Standard Review Plan Section 4.2, "Fuel System Design." 4. 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities." 5. 10 CFR Part 50, Appendix A, General Design Criterion 10, "Reactor Design." 6. 10 CFR Part 50, Appendix A, General Design 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,