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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s a nuclear reactor used to test design features, such as the testing required under 10 CFR 50.43(e). The prototype plant is similar to a FOAK or standard plant design in all features and size but may include additional safety features to protect the public and the plant staff from the possible consequences of accidents during the testing period. The purpose of the prototype plant is to perform testing of new or innovative design features in the new plant while also using the plant as a commercial nuclear power facility. Design qualification testing requirements may be met with 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 SDs, DCs, MLs, COLs, and OLs shall identify certain design qualification tests for the new advanced reactor designs that are used to mitigate accidents during the ITP testing period. For additional details, see Sections 6 and 7 of Appendix A of this guide for regulatory guidance on FOAK tests and design qualification tests. The ITP should also include testing the performance of non-safety related risk significant systems in passive plant designs that have special regulatory treatment. For additional details on the regulatory treatment of non-safety systems (RTNSS), refer to the RTNSS testing requirements in 10 CFR 50.36(c)(2)(ii)(D), GDCs (e.g., GDCs 3, 14, 34, 44, etc.) in Appendix A of 10 CFR Part 50, vendor test recommendations, and the guidance in NUREG-0800, “Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,” Section 19.3, “Regulatory Treatment of Non- Safety Systems (Passive Advanced Light Water Reactors)” (Ref. 9).