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. Ventilation, Recirculation, and Filter Systems (provided to minimize radioactive releases as a result of postulated accidents, including fuel handling accidents).9,10 8. Tanks and Other Sources of Water Used for the ECCS. Testing should include demonstrations of proper operation of associated alarms, indicators, controls, heating and chilling systems, and valves. 9. Containment Recirculation Fans (if used as part of post-accident containment heat removal systems). Testing should include demonstrations that the fans can operate in accordance with design requirements at the containment design peak accident pressure. 10. Ultimate Heat Sink: Testing should verify pump flow rates meet design acceptance criteria for removing plant heat loads during normal plant conditions and emergency design-basis accident conditions. 11. Passive Core Cooling System (PCCS)11 Preoperational testing of the PCCS should be performed and verified using the guidance in RG 1.79. Some example tests include: a. FOAK testing of pyrotechnic squib valves b. FOAK testing of other new valve designs (e.g., nozzle check valves) A-1.i. Primary and Secondary Containments Appropriate tests should be conducted to demonstrate that primary and secondary containments will function as designed. The testing methods and acceptance criteria should give due consideration to all systems and components that must operate for the containments to 9 These tests should be consistent with the provisions of Regulatory Guide 1.52, “Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants” (Ref. 22). 10 These tests should be consistent with the provisions of RG 1.140, “Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Normal Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants” (Ref. 23). 11 NUREG-1793, “Final Safety Evaluation