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:
see footnote 9); 5. leakage detection system sensitivity and capability meets TS leakage detection guidance in Regulatory Guide 1.45, “Guidance on Monitoring and Responding to Reactor Coolant System Leakage” (Ref. 25). This may include leakage detection system sensitivity and capability to detect RCS leakage from Steam Generators within the guidance in Nuclear Energy Institute (NEI) 97-06, “Steam Generator Program Guidelines,” (Ref. 26) and in Electric Power Research Institute (EPRI) TR-1008219, “PWR Primary-to-Secondary Leak Guidelines,” (Ref. 27) (e.g., radiation monitor detection sensitivity is 30 gallons per day or 1.25 gallons per hour). 6. radiation monitor computer system; 7. radiation data transmission to the emergency response data system; For radiation monitoring equipment that is used to perform automatic control functions, the tests should confirm, using established instrumentation set-points, that upon detecting elevated levels of radioactivity, the system initiates the proper automatic control features in ensuring the timely closures of isolation valves or dampers. Depending on design features, the logic sequence and interdependence of the actuation of automatic features should be tested as well when linked to radiation levels process streams and radioactive effluents. Such features may include monitoring deviations of in-plant dilution and exhaust flow rates in terminating releases Appendix A to DG-1259, Page A-15 or isolating process flows when deviations exceed preset limits. Other design features include monitoring the temperature of steam generator blowdown to protect resin beds from excessive temperatures; thereby, preventing a sudden loss in decontamination factors and releases of radioactivity above established limits and contamination of otherwise clean portions of plant systems. Tests should be conducted, as appropriate, to verify redundancy and electrical independence (see footnote 3). A-1.l. Integrity of Systems Outside of