Document: NUREG-0800
Document ID: 97b8d603-4b3f-40a3-9dbb-e89b68e654c6
Document Type: srp
Title: ANTICIPATED TRANSIENTS WITHOUT SCRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350327.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.8
CFR Part: 
CFR Title: 

Content:
apply: Rev. 1 - July 1981 USNRC STANDARD REVIEW PLAN Standard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responsible 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 FormaTt 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. 205 a. Criterion 10, which requires the reactor protection system to be designed with appropriate margin to assure that acceptable fuel design limits are not exceeded during normal operation including anticipated transients. b. Criterion 15, which requires that the reactor protection system be designed with sufficient margin to assure that the design conditions of the reactor coolant pressure boundary are not exceeded during normal operations includ- ing anticipated transients. c. Criterion 26, which requires two independent reactivity control systems. d. Criterion 27, which requires that the reactivity control systems have the combined capability of reliabily controlling reactivity changes to assure that under postulated accident conditions and with appropriate margin for stuck rods the core can be cooled. e. Criterion 29, which requires that the protection and reactivity control systems