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:
interface with this section as follows: 1. Specific SSCs subject to QA requirements are addressed in many other SRP subsections. (e.g., Sections 3.2.1, “Seismic Classification,” 4.5.1, “Control Rod Drive Structural Materials,” and 5.4.12, “Reactor Coolant System High Point Vents.”) 2. For COL reviews of operational programs, the review of the applicant’s implementation plan is performed under SRP Section 13.4, “Operational Programs.” The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. Appendix A, General Design Criterion 1 (GDC 1), “Quality Standards and Records,” to 10 CFR Part 50 requires that a QA program be established and implemented. 2. Appendix B to 10 CFR Part 50 specifies 18 quality criteria which must be addressed in a QAPD. 3. 10 CFR 50.34(b)(6)(ii) requires that the information on the controls to be used for a nuclear power plant include a discussion on how the applicable requirements of Appendix B will be satisfied. 4. 10 CFR 50.34(f)(3)(ii) and (iii) specify design and construction QA requirements which must be addressed in a QAPD. 5. 10 CFR 50.34(h) and 10 CFR 52.79(b) require that COL applicants or holders include an evaluation of the facility against the SRP that is in effect 6 months prior to the docket date of the application of a new facility. Alternatives to or differences from the SRP must be identified and justified in the application. These alternatives or differences are required to be discussed in the SER that is prepared by the NRC. 6. 10 CFR 50.54(a)(3)(ii) as it relates to changes to a QAPD that are not considered to be reductions in commitment, allows a licensee to use a QA alternative or exception approved by an NRC Safety Evaluation (SE) provided that the bases of the NRC approval are applicable to the licensee’s facility. 7. 10