Document: NRC Regulatory Guide
Document ID: de2a6863-3e00-4ade-b40d-9f1371ed9734
Document Type: regulatory_guide
Title: Power Levels of Nuclear Power Plants (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1221/ML12216A005.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.49
CFR Part: 
CFR Title: 

Content:
d power level are made for a slightly higher assumed power level to allow for possible instrument USAEC REGULATORY GUIDES Copies of published guides may be obtained by request indicating the divisions desired to the US. Atomic Energy Commission, Washington, D.C. 20645, Regulatory Guides are issued to describe and make available to the public Attention: Director of Regulatory Standards. Comments and suggestions for methods acceptable to the AEC Regulatory staff of implementing specific parts of Improvements in these guides we encouraged and should be sent to the Secretary the Commission's regulations, to delineate techniques used by the staff in of the Commission, U.S. Atomic Energy Commission, Washington, D.C. 20645, evaluating specific problems or postulated accidents, or to provide guidance to Attention: Chief, Public Proceedings Staff. applicents. Regulatory Guides am not substitutes for regulations and compliance VA" them is not required. Methods and solutions different from those set out in The guides are issued in the follvoing ton broad divisions: the guides will be acceptable if they provide a basis for the findings requisite to the eudiapos or continuance of a permit or license by the Commission. 1. Power Reactors 6. Products 2. Research and Test Reactors 7. Transportation 3. Fuels and Materials Facilities 8. Occupational Health Published gl=es will be revised periodicelly, ft appropriate. to accommodate 4. Environmental and Siting 9. Antitrust Review comments Indto reflect new information or experience. 5. Materials end Plant Protection 10. General errors in determing the power level. The Regulatory staff has determined that a margin of two percent of the licensed power level is adequate for this purpose. Analyses of the possible offsite radiological consequences of postulated design-basis accidents made to demonstrate acceptability of the site in accordance with 10 CFR Part 100 should be performed for at least 1.02 times the proposed licensed core power