Document: NRC Regulatory Guide
Document ID: a5ee4c78-1135-4bb6-8d54-e974a3402f87
Document Type: regulatory_guide
Title: An Approach for Plant-Specific, Risk-Informed Decisionmaking: Graded Quality Assurance
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1221/ML12216A017.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.176
CFR Part: 
CFR Title: 

Content:
plant-specific, risk-informed GQA submittal are presented in this section. The guidance is intended to help ensure the completeness of the information provided and to aid in shortening the time needed for the review process. Additional guidance on style, composition, and specifications of safety analysis reports is provided in the Introduction of Revision 3 of Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)" (Ref. 12). 4.1 Licensee Submittal Documentation To support the staff's conclusion that the proposed change is consistent with the key principles of risk- informed regulation and NRC staff expectations, the following information is expected to be submitted to the NRC. 4.1.1 GQA Program Change The licensee's existing QA program description contained in, or referenced by, the FSAR should be revised to describe the GQA program provisions. The submittal containing the proposed GQA provisions should contain the following. (1) A discussion of the essential implementation elements of the GQA program, the scope of potential SSCs that may be in the GQA program, and the basis for concluding that the overall GQA program provides reasonable confidence that SSCs remain capable of performing their intended function. (2) An overview discussion of the process and guidelines developed by the licensee to determine the safety-significance categorization of all SSCs within the GQA program scope as defined in this regulatory guide. (3) A statement of the role of the staff who perform the integrated assessment function (expert panel). (4) The process for determining the QA controls being applied to each safety-significance category of SSCs. (5) A description of the adjustments proposed as part of the GQA program and how the requirements of each of the criterion of Appendix B to 10 CFR Part 50 will be satisfied in a graded manner. The description should identify any exceptions to existing QA program commitments (such