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:
ividuals who are qualified to do inspections and who are independent from the actual performance of the work activity as discussed above. However, these changes cannot conflict with ASME Code-required inspections and examinations or other inspections and examinations specified in NRC regulations (e.g., use of the Authorized Nuclear Inspector services). The licensee may choose to reduce commitments to section 5.2.7 of ANS 3.2/ANSI N18.7 (Ref. 10) to perform post-work inspections for maintenance and modification activities depending upon the complexity of the work. Post-work inspections would then be performed for relatively complex maintenance and modifications. Other verifications such as applicable surveillance testing, receiving inspections, and inservice inspections would continue to be performed for the low safety-significant item. Licensees may propose to reduce their require- ments regarding personnel who perform inspections on low safety-significant items. Those inspection personnel will need to be experienced, task-qualified journeymen, or supervisors who did not perform or directly supervise the activity being inspected. These personnel will need to receive training in the quality organization's inspection procedures, processes, and methods in accordance with a training program approved by the quality organization. The quality organization will need to provide periodic oversight of these inspectors. This provision would also not be applicable for staff who perform nondestructive examinations. 3.2.3 Records and Documentation . Documentation, such as procedures and design packages, for low safety-significant SSCs may be less detailed than for high safety-significant items. In assessing the level of detail specified in procedures or actual packages related to low safety-significant items, there should be enough evidentiary detail to maintain plant design and configuration control. Further, 0 1.176-16 sufficient records need to be maintained to evaluate