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:
of the next level unless TS limits are more restrictive. 5. Perform general surveys of plant systems and equipment to determine that they are operating within expected values. 6. Check for unexpected radioactivity in process systems and effluents. 7. Verify reactor coolant leak checks and ESF system leakage checks are within FSAR Chapter 15 accident analysis limits. 8. Perform primary to secondary leakage detection testing through steam generators (PWR only) 9. Verify that acoustic resonance criteria are not reached in the main steam system. 10. Monitor potential adverse flow effects from acoustic resonance and hydraulic loading on reactor internals (including the steam dryer for BWR plants) and flow-induced vibration of piping and components in the reactor coolant, main steam, and main feedwater systems with procedural instructions to reduce power to an acceptable level where evaluation of plant data indicates that structural limits for piping or components might be reached during power ascension. Structural capability of piping and components will be demonstrated prior to continuing power ascension. Appendix C to DG-1259, Page C-9 11. Review the completed testing program at each plateau; perform preliminary evaluations, including extrapolation of minimum departure from nucleate boiling ratio and maximum linear heat rate values to the high flux trip set point for the next power level; and obtain the required management approvals before ascending to the next power level or test condition.