Document: NRC Regulatory Guide
Document ID: 47b09be1-4bf8-45f9-a099-7fed871c09bd
Document Type: regulatory_guide
Title: Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2114/ML21140A055.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.175
CFR Part: 
CFR Title: 

Content:
onstrate that the proposed RI-IST program would provide an acceptable level of quality and safety. o 10 CFR Part 50, Appendix B, Criterion XVI, “Corrective Action,” which states, “Measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.” • 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” provides regulations for the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. Related Guidance • NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition” (SRP) (Ref. 5), provides guidance to the NRC staff in performing safety reviews of construction permit or operating license applications (including requests for amendments) under 10 CFR Part 50 and early site permit, design certification, combined license, standard design approval, or manufacturing license applications under 10 CFR Part 52 (including requests for amendments). Note that the SRP Section 3.9.7, “Risk-Informed Inservice Testing,” addresses RI-IST, consistent with the guidance in this RG (Ref. 6). • NUREG-1482, “Guidelines for Inservice Testing at Nuclear Power Plants—Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants—Final Report,” (Ref. 7), provides guidance for OM Code inquiries, the inservice examination and testing of snubbers, pump and valve IST, the use of ASME Code Cases, conditions on the use of the OM Code, guidance for OM Code noncompliance, requests for alternatives to the OM Code at operating commercial nuclear power plants, and the development of IST programs for new reactors. • NUREG-1855, “Guidance on the