Document: NRC Regulatory Guide
Document ID: bd0ffb9e-22f8-46a4-ab36-f5cffd435ed7
Document Type: regulatory_guide
Title: Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0037/ML003739601.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.3
CFR Part: 
CFR Title: 

Content:
evaluated on an individual case basis. e. The primary containment should be assumed to leak at the leak rate incorporated or to be incorporated in the technical specifications for the duration of the USAEC REGULATORY GUIDES Copies of published s nay be obtained by request Indicating the divisions desired to the US. Atomic Energy Commission, Washington, D.C. 20645, Regulatory Guides are issued to descobe and mal available to the Public Attention: Director of Regulatory Standrds. Comments and suggestions for methods acceptable to the AEC Regulatory staff of implementing specific parts of Improvements In thes guides we encouraged and should be sent to the Secretary ths Commission's regulations, to delineate techniques used by the staff in of the Commission, US. Atomic Energy Commission, Washington, D.C. 20645, eveluating specific problems or postulatedi accidents, or to provide guidance to Attention: Chief, Public Proceedings Staff. applicants. Regulatory Guides are not substitutes for regulations end compliance with them is not required. Methods end solutions different from thorn set out in The auides are issued in the following ten broad divisions: the guldes will be acceptable If they provide a basis for the findings requisite to the issuance 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 guide will be revised periodically, as appropriate, to accommodate 4. Environmental and Siting 9. Antitrust Review comments to reflect new information or experience. 5. Materials and Plant Protection 10. General accident. 1 The leakage should be assumed to pass directly to the emergency exhaust system without mixing_2 in the surrounding reactor building atmosphere and should then be assumed to be released as an elevated plume for those facilities with stacks. ' f. No credit should be given for retention of iodine in the