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Regulations, Standard Review Plan, and SECY Paper Regarding Quality Assurance for New Reactors

The "Quality Assurance Criteria for Nuclear Plants and Fuel Reprocessing Plants," set forth in Appendix B to Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50), must be implemented for activities affecting safety-related plant equipment. Licensees are also required to develop, and control changes to, their quality assurance (QA) programs, as stated in 10 CFR 50.54(a)(1). In addition, 10 CFR 50.34(b)(6)(ii) requires that a licensees description of its QA program for a nuclear power plant must include a discussion of how the applicable requirements of Appendix B will be satisfied. For detail, see the following topics on this page:

Code of Federal Regulations
Standard Review Plan (NUREG-0800)
SECY Paper

Code of Federal Regulations

Part	Subject
Appendix A to 10 CFR Part 50	General Design Criteria
Appendix B to 10 CFR Part 50	Main QA Regulation
10 CFR Part 21	Reporting of Defects and Noncompliance
10 CFR 50.4(b)(7)	Written Communications - Quality Assurance Related Submittals
10 CFR 50.34(b)(6)(ii)	QA Program Description
10 CFR 50.34(f)(3)(ii) and 10 CFR 50.34(f)(3)(iii)	Requirements Related to the Incident at Three Mile Island (TMI) (I.F.1 and I.F.2)
10 CFR 50.36(c)(5)	Administrative Controls
10 CFR 50.54(a)(1)	QA Program Requirement
10 CFR 50.54(a)(2)	Submittal of QA Program Description
10 CFR 50.54(a)(3)	QA Program Description Change Control
10 CFR 50.54(a)(4)	Reductions in Commitments in QA Program
10 CFR 50.55(e)	Evaluation of Defects and Failures To Comply Associated with a Substantial Safety Hazard
10 CFR 50.55a	Codes and Standards
10 CFR 50.71(e)	Maintenance of Records
10 CFR 52.17(a)(xi)	QA Program Description (Early Site Permits)
10 CFR 52.47(a)(8)	TMI-Related Requirements (Design Certifications)
10 CFR 52.47(a)(19)	QA Program Description (Design Certifications)
10 CFR 52.79(a)(17)	TMI-Related Requirements (Combined Licenses)
10 CFR 52.79(a)(25)	QA Program Description (Combined Licenses)

Standard Review Plan (NUREG-800)

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Section	Title	Rev.	Date Updated
17.1	Quality Assurance During the Design and Construction Phases	Rev. 2	07/1981
17.2	Quality Assurance During the Operations Phase	Rev. 2	07/1981
17.3	Quality Assurance Program Description	Rev. 0	08/1990
17.5	Quality Assurance Program Description - Design Certification, Early Site Permit, and New License Applicants	Initial	03/2007

SECY Paper

The staff of the U.S. Nuclear Regulatory Commission (NRC) performed a review of international QA standards (ISO 9001-2000) against the existing framework of Appendix B to 10 CFR Part 50, and assessed approaches for adopting international quality standards for safety-related components in nuclear power plants into the existing regulatory framework. This review is documented in SECY-03-0117.