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:
res of cooled components within design limits with the minimum design capability of cooling system components available (100 percent). x. Demonstrate adequate beginning of life performance margins for auxiliary systems required to support the operation of engineered safety features or maintain the environment in spaces that house engineered safety features to provide assurance that the engineered safety features will be capable of performing their design functions over the range of design capability of operable components in these auxiliary systems (50 percent, 100 percent). y. Calibrate, as required, and verify the proper operation of important instrumentation systems, including: 1. reactor coolant system flow; 2. core flow, level, and temperature; 3. in-core and ex-core neutron flux; and 4. instruments and systems used to calculate the thermal power level (heat balance) of the reactor (25 percent, 50 percent, 75 percent, 100 percent). z. Demonstrate that process and effluent radiation monitoring systems or airborne activity monitoring system, are responding correctly by performing independent laboratory testing or other analyses. aa. Demonstrate that chemical and radiochemical control systems function in accordance with design and sample to establish that reactor coolant system and secondary coolant system limits are not exceeded (25 percent, 50 percent, 75 percent, 100 percent). bb. Conduct neutron and gamma radiation surveys to establish the adequacy of the airborne activity monitoring system, shielding surveys, access controls, and identification of high- radiation zones as defined in 10 CFR Part 20, Technical Specifications, RG 1.69, “Concrete Radiation Shields and Generic Shield Testing for Nuclear Power Plants,” (Ref. 32) and RG 8.38, “Control of Access 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