Document: NUREG-0800
Document ID: cd56bdba-c3ad-487c-9736-aba8587452af
Document Type: srp
Title: QUALITY ASSURANCE PROGRAM DESCRIPTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350376.pdf
Revision Date: 2023-06
Chapter: 17
Section ID: 17.3
CFR Part: 
CFR Title: 

Content:
tandard plant designer's QA program. The staff will continue to review licensee-proposed revisions of quality assurance program descriptions that have been accepted by the staff in accordance with SRP Sections 17.1 or 17.2 against their original acceptance criteria. However, current licensees may adopt Section 17.3 if they choose to do so. VI. REFERENCES A. Regulatory guidance issued in response to Appendix B of 10 CFR Part 50: 1. Regulatory Guide 1.8, "Personnel Selection and Training." 2. Regulatory Guide 1.26, "Quality Group Classification, and Standards. for Water-, Steam-, and Radioactive-Waste- Containing Components of Nuclear Power Plants. 3. Regulatory Guide 1.28, "Quality Assurance Program Requirements (Design and Construction)," using NQA-1 and NQA-2. 4. Regulatory Guide' 1.29, "Seismic Design Classification." 5. Regulatory Guide 1.33, "Quality Assurance Program Requirements (operations)," with appropriate substitution of NQA-1 and NQA- 2 for N-45.2 and its daughter standards. 6. Regulatory Guide 1.152, "Criteria for Programmable Digital Computer System Software in Safety-Related Systems of Nuclear Power Plants." 7. Generic Letter 89-02 and its endorsement of EPRI NP-5652, "Guideline for the Utilization of Commercial-Grade Items in Nuclear Safety-Related Applications (NCIG-07)." B. Other Programmatic QA Guidance: 1. Fire protection QA controls are to be in accordance with Regulatory Positions 2 and 4 of Branch Technical Position CMEB 9.5-1 as given in SRP Section 9.5.1. 2. Radioactive waste QA controls are to be in accordance with Regulatory Position 6 of Regulatory Guide 1.143, "Design 17.3-17 Rev. 0 - August 1990 , . .2 Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light Water-Cooled Nuclear Power Plants." 3. QA controls are required by a commitment to Regulatory Guide 1.36, "Nonmetallic Thermal Insulation for Austenitic Stainless Steel." 4. Regulatory Guide 1.54, "Quality Assurance Requirements for Protective