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:
ately frequent events) conditions and postulated accident conditions and for maintaining the reactor in a safe condition for an extended shutdown period following such conditions; 3. they will be used to establish conformance with safety limits or limiting conditions for operation that will be included in the facility’s technical specifications; 4. they are classified as engineered safety features or will be relied on to support or ensure the operation of engineered safety features within design limits; 5. they are assumed to function or for which credit is taken in the accident analysis of the facility, as described in the FSAR; 6. they will be used to process, store, control, or limit the release of radioactive materials; and 7. they are relied upon to maintain their structural integrity during normal operation, anticipated transients, simulated test parameters, and design-basis event conditions to avoid damage to safety-related SSCs. DG-1259, Page 8 Appendix A to this regulatory guide provides a representative list of systems to be tested, as well as performance capabilities important to safety, as defined by Appendix A to 10 CFR Part 50, which should be demonstrated for light-water cooled nuclear power plants. However, licensees should also conduct in-plant testing to verify the adequacy of the construction, installation, and design for other systems and design features not listed in Appendix A if those systems or design features meet any of the above criteria. The ITP may be developed and implemented using a graded approach, which should ensure that the greatest attention is given to the most safety significant SSCs, such as those considered to be engineered safety features. This graded approach should include testing for non safety related risk significant SSCs. 2. Prerequisites for Testing The construction or installation of SSCs should be essentially complete (to the degree that outstanding construction items could not be expected to affect the validity of