Document: NUREG-0800
Document ID: f5fcd424-bea6-4f79-b002-f91d93dd4c9e
Document Type: srp
Title: QUALITY ASSURANCE PROGRAM DESCRIPTION - DESIGN CERTIFICATION,
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190019.pdf
Revision Date: 2023-06
Chapter: 17
Section ID: 17.5
CFR Part: 
CFR Title: 

Content:
or holder’s QA program that highlights the more important aspects of the program should also be provided in the SER. For DC and COL reviews, the findings will also summarize the staff’s evaluation of COL action items relevant to this SRP section. V. IMPLEMENTATION 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apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. 17.5-48 March 2007 VI. REFERENCES 1. NRC Letter to All Holders of Operating Licenses and Construction Permits for Nuclear Power Reactors, “Actions to Improve the Detection of Counterfeit and Fraudulently Marketed Products (Generic Letter 89-02).” 2. NRC Letter to All Holders of Operating Licenses and Construction Permits for Nuclear Power Reactors, “Licensee Commercial-Grade Procurement and Dedication Programs (Generic Letter 91-05).” 3. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” 4. American Society of Mechanical Engineers. “Quality Assurance Program Requirements for Nuclear Facility Applications,” ANSI/ASME Standard NQA -1, Washington, DC. 1983. 5. 10 CFR 50.34, “Contents of Applications; Technical Information.” 6. 10 CFR 50.55a, “Codes and Standards.” 7. 10 CFR Part 50, Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion 1, “Quality Standards and Records.” 8. 10 CFR 50.69, “Risk-Informed Categorization of Structures, Systems and Components of Nuclear Power