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:
axial power peaking factors, maximum average planar linear heat generation rate, minimum critical power ratio, quadrant power tilt, and other important parameters are in accordance with design values throughout the permissible range of power to flow conditions (25 percent, 50 percent, 75 percent, 100 percent). Appendix A to DG-1259, Page A-25 c. Demonstrate that core limits will not be exceeded during or following an exchange of control rod patterns that will be permitted during operation. (The demonstration test should be conducted at the highest power level at which control rod pattern exchanges will be allowed during plant operation.) d. Demonstrate the capabilities of plant features (such as part length control rods) and procedures for controlling core xenon transients. Acceptance criteria for the test should account for expected changes in core performance throughout core life (75 percent to 85 percent) (PWR). The results of xenon oscillation tests performed at plants of essentially identical design can be used to substitute or supplement this testing. e. Demonstrate that core thermal and nuclear parameters are in accordance with predictions with a single high-worth rod fully inserted and during and following return of the rod to its bank position (50 percent). f. Demonstrate that control rod sequencers, control rod worth minimizers, and rod withdrawal block functions operate in accordance with design, if not previously demonstrated (25 percent) (BWR). g. Check rod scram times from data recorded during scrams that occur during the startup test phase to determine that the scram times remain within allowable limits. h. Demonstrate the capability and/or sensitivity, as appropriate for the facility design of incore and ex-core neutron flux instrumentation, to detect a control rod misalignment equal to or less than the TS limits (50 percent, 100 percent) (PWR). i. Verify that plant performance is as expected for rod runback and partial scram. j. Demonstrate that