Document: NUREG-0800
Document ID: fb2c3684-8fec-4057-868d-a766b49899b7
Document Type: srp
Title: INTRODUCTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350113.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0
CFR Part: 
CFR Title: 

Content:
. 2 - July 1981 USNRC STANDARD REVIEW PLAN Standard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff responqible 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. Events such as fires, floods, storms, or earthquakes are not explicitly considered in the review of anticipated operational occurrences and postulated accidents in Chapter 15. Rather, the requirements to design for these events are reviewed under other SRP sections, as listed in Table 15-1 (attached). The reviewers are responsible for the selection and emphasis of aspects of the reviews of anticipated operational occurrences and postulated accidents in this chapter. Judgment on the areas to be given attention during each review is based on an inspection of the information provided, the similarity of this material to that recently reviewed on other plants, and whether items of special or unique safety significance are involved. The Reactor Systems Branch reviews the majority of anticipated operational occurrences and postulated accidents as indicated in the SRP sections for Chapter 15. Various