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:
ith the minimum availability of ventilation system components for which the system is designed to operate. k. Demonstrate the operability of steam-driven engineered safety features, plant auxiliaries, and power conversion equipment. l. Demonstrate the operability, including stroke times, of main and branch steam-line valves and bypass valves used for protective isolation functions at rated temperature and pressure conditions. m. Demonstrate the operability of the main steam-line isolation valve leakage control system (BWR, during hot standby conditions). n. Demonstrate the operability of the control room computer system. o. Conduct control rod scram time testing at rated temperature in the reactor coolant system (if not previously conducted). p. Demonstrate the operability of pressurizer and main steam system relief valves at rated temperature. q. Demonstrate the operability of reactor coolant system purification and cleanup systems including tests for flow rates, heat transfer capability, purification and cleanup capability and pressure drops. r. Demonstrate the operability of residual or decay heat removal systems, including auxiliary or emergency feedwater, atmospheric steam dump valves (PWR), and turbine bypass valves and the RCIC system or isolation condenser system (BWR). s. Conduct vibration measurements of reactor vessel internals (see footnote 1) and reactor coolant system components (if not previously conducted). t. Perform natural circulation tests of the reactor coolant system to confirm that the design heat removal, boron mixing plant cool down/depressurization, and stable natural circulation conditions are maintained throughout the test or by comparison of the plant’s Appendix A to DG-1259, Page A-24 reactor coolant system hydraulic data to a reference prototype plant of similar design and configuration (PWR). u. Demonstrate the operability of major or principal plant control systems, as appropriate. A-5. Power-Ascension Testing Licensees should