Document: NRC Regulatory Guide
Document ID: 74c49394-8dbf-46e7-b62a-b85de93b47d8
Document Type: regulatory_guide
Title: Initial Test Programs for Water-Cooled Nuclear Power Plants + HISTORY - HISTORY 11/2012 – DG-1259 , Proposed Revision 4 11/2006 – DG-1166 , Proposed Revision 3 (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1229/ML12298A071.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.68
CFR Part: 
CFR Title: 

Content:
K) Testing First-of-a-kind (FOAK) tests are defined as new, unique, or special tests for new design features in plants licensed under 10 CFR Part 50 or 10 CFR Part 52. If certain SSCs are new, unique, or special, principal design features that will be used in the facility, the ITP functional testing requirements necessary to verify FOAK test performance should be identified at an early date in the SD, DC, ML, COL, or OL application process to account for the final design of the plant. Some new plant designs licensed under 10 CFR Part 52 have passive plant design features and FOAK tests for systems that are safety-related or important to safety. For example, some new passive plant designs use large pyrotechnic-actuated valves with new designs in safety significant applications. Consequently, each new SD, DC, ML, COL, or OL application for an advanced plant licensed under 10 CFR Part 50 or 10 CFR Part 52 should identify new FOAK tests in the given plant. This regulatory guide does not identify specific FOAK tests but new SD, DC, ML, COL, or OL applicants may identify specific FOAK tests for new, unique or special plant design features that require additional design verification testing during the ITP to verify that as-built test acceptance criteria are met. A-7. Design Qualification Tests for Advanced Reactors Design qualification tests for advanced reactors are used to demonstrate the performance of new safety features for nuclear reactor plants that differ significantly from evolutionary light water reactors or that use simplified, inherent, passive, or other innovative means to accomplish their safety functions. The statement of considerations (SOC) for “Licenses, Certifications and Approvals for Nuclear power Plants – Final Rule,” Federal Register Notice (FRN) Volume 72, No. 166, dated August 28, 2007, (Ref. 35), pages Appendix A to DG-1259, Page A-30 49369 and 49370, states, in part, that design qualification test requirements were included in 10 CFR Part