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
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CFR Title: 

Content:
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 52 to demonstrate the performance of new safety features for nuclear power plants (advanced reactors) that differ significantly from evolutionary light water reactors or that use simplified, inherent, passive or other innovative means to accomplish their safety functions. Design qualification test requirements were included in 10 CFR Part 52 to ensure that new safety features will perform as predicted in the licensee’s FSAR, to provide sufficient data to validate analytical codes, and to ensure that the effects of systems interactions are acceptable. The design qualification testing requirements may be met with either separate effects or integral system tests, prototype tests, or a combination of tests, analyses, and operating experience. These requirements implement the Commission’s policy on proof of performance testing for all advanced reactors with the goal of resolving all safety issues before authorizing construction. Some prototype plant tests or FOAK tests may not be resolved until after fuel load and plant startup. The supplier of a DC may use integral system test facilities to demonstrate through scale model testing and simulation codes that certain as-built DC SSCs will meet their design and test acceptance criteria. If integral system tests and simulation codes cannot adequately demonstrate proof of performance testing, then the COL applicant may identify additional prototype plant tests or FOAK tests during the ITP to verify as-built test acceptance criteria are met. Under 10 CFR 50.2, “Definitions,” the term “Prototype plant” means a nuclear reactor that is used to test design features, such as the testing required under 10 CFR 50.43(e). The prototype plant is similar to FOAK or standard plant design in all features and size, but may include