Document: NUREG-0800
Document ID: 18897384-49d0-41ca-b285-0b1201052b03
Document Type: srp
Title: CONTROL ROD MISOPERATION (SYSTEM MALFUNCTION OR OPERATOR ERROR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350372.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.3
CFR Part: 
CFR Title: 

Content:
ble for the review of applications to construct and operate nuclear power plants. These documents are made available to the public as part of the Commission's policy to Inform the nuclear Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically, as appropriate, to accommodate comments and to reflect new informa- tion and experience. Comments and suggestions for Improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Washington, D.C. 2 5. The input to the calculations, including rod worths, power distributions, and feedback coefficients, and evidence of the conservatism of the input. 6. Results of the analyses including, for each of the transients considered, plots of the time history of reactor power, reactor vessel pressure, critical heat flux for the limiting fuel rod, and maximum fuel centerline temperature or linear heat generation rate. II. ACCEPTANCE CRITERIA 1. The following General Design Criteria (Ref. 1) apply: a. Criterion IC, which requires that specified acceptable fuel design limits are not to be exceeded during normal operation, including the effects of anticipated operational occurrences. b. Criterion 20, which requires that the protection system initiate auto- matically appropriate systems to assure that specified acceptable fuel design limits are not exceeded as a result of anticipated operational occurrences. c. Criterion 25, which requires that the reactor protection system be designed to assure that specified acceptable fuel design limits are not exceeded in