Power Reactors (Division 1): Regulatory Guides 1.81 - 1.100
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 comments from stakeholders on any Regulatory Guide at any time. Comments 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.
|1.81||Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants||1||01/1975|
|1.82||Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident||4||03/2012||04/2012|
|1.83||Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes
(Withdrawn -- See 74 FR 58324, 11/12/2009)
|1.84||Design, Fabrication, and Materials Code Case Acceptability, ASME Section III||35
|1.85||Materials code case Acceptability - - ASME Section III, Division 1
(Withdrawn 69 FR 34202 06/18/2004)
|1.86||Termination of Operating Licenses for Nuclear Reactors||--||06/1974||12/2011|
|1.87||Guidance for Construction of Class 1 Components in Elevated-Temperature Reactors||--||06/1975||11/2010|
|1.88||Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Record
(Withdrawn -- See 56 FR 36175, 07/31/1991)
|1.89||Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants||1||06/1984|
|1.90||Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons||2||11/2012|
|1.91||Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants||2||04/2013|
|1.92||Combining Modal Responses and Spatial Components in Seismic Response Analysis||3||09/2012|
|1.93||Availability of Electric Power Sources||1||03/2012|
|1.94||Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants
(Withdrawn -- See 75 FR 54921, 09/09/2010)
|1.95||Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release
(Withdrawn 67 FR 939 01/08/2002)
|1.96||Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants||1||06/1976|
|1.97||Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants||4||06/2006||03/2013|
|1.98||Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor (for Comment)||--||03/1976||10/2010|
|1.99||Radiation Embrittlement of Reactor Vessel Materials||2||05/1988|
|1.100||Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants||3||09/2009||09/2009|