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:
y Guide 1.41, “Preoperational Testing of Redundant Onsite Electric Power Systems to Verify Proper Load Group Assignments,” (Ref. 16) should be used as guidance for appropriate tests. Appendix A to DG-1259, Page A-5 other systems following off-normal conditions or anticipated transients, including reactor scram. 2. Verify the operability of systems and design features provided for makeup of coolant, to dissipate residual heat, to cool the reactor down to a cold-shutdown condition, and to maintain long-term cooling. 3. Tests should be conducted, as appropriate, to verify redundancy and electrical independence (See Footnote 3). The following list illustrates the systems and components that should be tested: a. turbine bypass valves b. steam line atmospheric c. dump valves d. relief valves e. safety valves f. decay and heat removal system g. reactor core isolation cooling (RCIC) system h. main steam isolation valves, branch steam isolation valves, and non return valves i. auxiliary feedwater systems j. condensate storage system k. emergency cooling towers ultimate heat sink l. cooling water systems m. isolation condenser system. Testing should include demonstrations that the systems will meet design performance requirements at approximately normal operating primary and secondary coolant system pressures and temperatures and over the range of expected reactor pressure vessel and steam generator levels. Operability of system pumps, valves, controls, and instrumentation should be demonstrated and, to the extent practical, testing should provide reasonable assurance that flow instabilities (e.g., water hammer), including flow inducted vibration, will not occur in system components or piping, or inside the reactor pressure vessel, steam generators, and other heat exchangers during normal system startup and operation. A-1.e. Power Conversion System The power conversion system includes all components provided to channel reactor thermal energy during normal operation from