Power Reactors (Division 1): Regulatory Guides 1.181 - 1.200
This page lists the number, title, publication date, and revisions for each regulatory guide in Division 1, "Power Reactors," with references to draft guides and related documents (where applicable).
See also Draft Regulatory Guides for Division 1.
See NRC Regulatory Guides for more general information.
Reviewed (last column on table) means that the NRC has reviewed these guides and has determined that they are acceptable for continued use. The NRC encourages suggestions from stakeholders regarding any Regulatory Guide or development of new guides at any time. Suggestions received in this manner will be reviewed upon receipt, but will be fully evaluated during the next periodic review of the affect guides. Currently, Regulatory Guides are reviewed on a 5 year basis. In certain cases, a Regulatory Guide will be looked at before the 5 year period has passed.
|1.181||Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)||--||09/1999||01/2010|
|1.182||Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants
(Withdrawn – See 77 FR 70846, 11/27/2012)
|1.183||Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors||--||07/2000|
|1.184||Decommissioning of Nuclear Power Reactors||1||10/2013|
|1.185||Standard Format and Content for Post-Shutdown Decommissioning Activities Report||1||06/2013|
|1.186||Guidance and Examples for Identifying 10 CFR 50.2 Design Bases||--||12/2000||06/2011|
|1.187||Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments||--||11/2000||04/2011|
|1.188||Standard Format and Content for Applications To Renew Nuclear Power Plant Operating Licenses||1||09/2005||04/2010|
|1.189||Fire Protection for Nuclear Power Plants||2||10/2009|
|1.190||Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence||--||03/2001||05/2013
|1.191||Fire Protection Program for Nuclear Power Plants During Decommissioning and Permanent Shutdown||--||05/2001||10/2011|
|1.192||Operation and Maintenance Code Case Acceptability, ASME OM Code||--||06/2003|
|1.193||ASME Code Cases Not Approved for Use||3||10/2010|
|1.194||Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants||--||06/2003|
|1.195||Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors||--||05/2003||08/2011|
|1.196||Control Room Habitability at Light-Water Nuclear Power Reactors||1||01/2007||08/2013|
|1.197||Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors||--||05/2003||04/2010|
|1.198||Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites||--||11/2003|
|1.199||Anchoring Components and Structural Supports in Concrete||--||11/2003|
|1.200||An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities||2||03/2009|