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:
t a control rod misalignment equal to or less than the TS limits (50 percent, 100 percent) (PWR). i. Verify that plant performance is as expected for rod runback and partial scram. j. Demonstrate that ECCS high pressure coolant injection (HPCI) systems (e.g., HPCI for BWR/2-4, high pressure core spray (HPCS) for BWR/5-6, high pressure core flooder (HPCF) for ABWR) can start under simulated accident conditions and inject into the reactor coolant system as designed. This test should be conducted at a power level in the 25 percent to 50 percent range for BWRs with steam- or electric driven pumps, if not previously conducted. See RG 1.79 and RG 1.79.1 for additional details. k. Demonstrate the design capability of all systems and components provided to remove residual or decay heat from the reactor coolant system, including the turbine bypass system, atmospheric steam dump valves, residual heat removal system in steam condensing mode, RCIC system (BWR/3-6, ABWR), isolation condenser system (BWR/2, ESBWR), reactor water cleanup shutdown cooling system non-regenerative heat exchangers (ESBWR), and auxiliary feedwater system. Testing of the auxiliary or emergency feedwater system should include provisions to provide reasonable assurance that excessive flow instabilities (e.g., water hammer) will not occur during subsequent normal system startup and operation (before exceeding 25-percent power). See RG 1.79 and RG 1.79.1 for additional details. l. Demonstrate that the reactor coolant system operates in accordance with design. Sufficient measurements and evaluations should be conducted with the plant at steady state conditions to establish that flow rates, reverse flows through idle loops or jet pumps, core flow, differential pressures across the core and major components in the reactor coolant system, vibration levels of reactor coolant system components, and other Appendix A to DG-1259, Page A-26 important parameters are in agreement with design values, if not previously