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:
7 information in the referenced standard, if appropriately justified and consistent with current regulatory practice. Appendix A references existing regulatory guides that are applicable to ITPs. The referenced guides provide detailed guidance for particular tests. Harmonization with International Standards The International Atomic Energy Agency (IAEA) has established a series of safety guides and standards constituting a high level of safety for protecting people and the environment. IAEA safety guides are international standards to help users striving to achieve high levels of safety. Pertinent to this regulatory guide, IAEA Safety Guide NS-G-2.9, “Commissioning of Nuclear Power Plants,” issued June 2003, (Ref. 10) addresses tests to be performed during commissioning of a nuclear power plant. This regulatory guide incorporates similar testing program recommendations and is consistent with the basic safety principles provided in IAEA Safety Guide NS-G-2.9. C. STAFF REGULATORY GUIDANCE 1. Criteria for Selection of Defense in Depth Plant Functions to be Tested Pursuant to requirements of 10 CFR Parts 50 and 52, each applicant or licensee should prepare and conduct an ITP to demonstrate that the plant can be operated in accordance with design requirements important to safety as defined by Appendix A to 10 CFR Part 50. Suitable tests should be conducted to verify the performance capabilities, as delineated in Appendix A to 10 CFR Part 50, of SSCs that meet one or more of the following criteria: 1. they will be used for shutdown and cool down of the reactor under normal plant conditions and for maintaining the reactor in a safe condition for an extended shutdown period; 2. they will be used for shutdown and cool down of the reactor under transient (infrequent or moderately 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