Document: NUREG-0800
Document ID: a7fafe76-5570-446b-96dd-3e53ec9bccb3
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340663.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4
CFR Part: 
CFR Title: 

Content:
dial, and local distributions and peaking factors to be used in the transient Rev. 2 - July 1981 USNRC STANDARD REVIEW PLAN Standard review plans are prepared for the guidance of ttw Office of Nuclear Reactor Regulation staff responsible for the review of applicadons to Constuct nd operate nucleer power plants. These documents are made aiable to the public as part of the Commision policy to ifor the nuclear Industry and te general public of regulatory procedure and policies. Standard rviw pans are not substite for regulatr guides or the Commission's regulations and compliance with them Is not required. The standard pan sectons are ked to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not a Ions of the Standard Fomat have a corresponding review plan. Published standard review plans will be reved periodically, a 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. O.C. C. and accident analyses The effects of phenomena such as fuel densification should be included in these distributions and factors. c. The translation of the design power distributions into operating power distributions, including instrument-calculation correlations, operat- ing procedures and measurements, and necessary limits on these operations. d. The requirements for instruments, the calibration and calculations involved in their use, and the uncertainties involved in translation of instrument readings into power distributions. e. Limits and setpoints for actions, alarms, or scram for the instrument systems and demonstration that these systems can maintain the reactor within design power distribution limits. f. Measurements in previous reactors and critical experiments and their use in the uncertainty analyses, and measurements to be made on the reactor under