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:
Power Reactors,” to 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities.” Appendix A to DG-1259, Page A-12 21. containment penetration cooling system tests. In general, the test sequence should proceed from the low-pressure test to the accident- pressure test, or sufficient time should be allowed between tests to ensure that out-gassing from concrete or components within the containment will not affect the test results. A-1.j. Instrumentation and Control Systems The nomenclature applied to instrumentation and control systems varies widely with different plant designs; however, the primary functions are similar for light-water-cooled reactors. The principal functions of instrumentation and control systems are to: 1. control the normal operation of the facility within design limits; 2. provide information and alarms in the control room to monitor the operation and status of the facility and permit corrective actions to be taken for off normal plant conditions; 3. establish that the facility is operating within design and license limits; 4. permit or support the correct operation of engineered safety features; and 5. monitor and record important parameters during and following postulated accidents. Tests also should verify that instruments for RCS leakage and secondary leakage are capable of detecting the required leakage rates using concentrations of radioactive material expected to be present in the RCS during routine operations. In the design of nuclear power plants, postulated accident assumptions are often explicitly or implicitly bounded by the design of instrumentation and control systems (e.g., pressurizer level or feedwater flow control). In such cases, operation of the instrumentation and controls over the design operating range should be performed, and the effects of limiting malfunctions or failures should be simulated to demonstrate the adequacy of design and installation and the validity of accident analysis assumptions.