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:
to High and Very High Radiation Areas in Nuclear Power Plants” (Ref. 33) (50 percent, 100 percent). cc. Demonstrate that gaseous and liquid radioactive waste processing, storage, and release systems operate in accordance with design. dd. Demonstrate the capability to shut down and maintain the reactor in a hot standby condition from outside the control room, using the minimum shift crew, as well as the Appendix A to DG-1259, Page A-28 potential capability to place the reactor in a cold shutdown condition16 (greater than or equal to a 10 percent generator load). ee. Demonstrate that primary containment inerting and purge systems operate in accordance with design, if not previously demonstrated. ff. Demonstrate or verify that important ventilation and air conditioning systems, including those for the primary containment and steam-line tunnel, continue to maintain their service areas within the design limits (50 percent, 100 percent). gg. If appropriate for the facility design, conduct tests to determine the operability of equipment provided for anticipated transient without scram, if not previously determined (25 percent). hh. Demonstrate that the dynamic response of the plant to the design load swings for the facility, including step and ramp changes, is in accordance with design (25 percent, 50 percent, 75 percent, 100 percent). ii. Demonstrate that the dynamic response of the plant is in accordance with design for limiting reactor coolant pump trips and/or closure of reactor coolant system flow-control valves (BWR). The method for initiating the pump trip or control valve closure should result in the fastest credible coast down in flow for the system (100 percent). jj. Demonstrate that the dynamic response of the plant is in accordance with design for a condition of loss of turbine generator coincident with loss of all sources of offsite power (i.e., station blackout for passive plants with no emergency diesel generators) (in the range of 10-20 percent power).