Power Reactors (Division 1): Regulatory Guides 1.61 - 1.80
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 dates (the last column in the table) are when the staff completed a periodic review of the associated guide. Regulatory Guides are reviewed about every 5 years, although in some cases a guide will reviewed before the normal 5 year period. The NRC began these reviews in 2010, and began posting the results of its reviews on this site in 2013. The review dates are hyperlinked to the review memorandum, which provide useful information about the status and any known issues with the associated regulatory guide.
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 typically be fully evaluated during the next periodic review of the affect guides.
|1.61||Damping Values for Seismic Design of Nuclear Power Plants||1||03/2007|
|1.62||Manual Initiation of Protective Actions||
|1.63||Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants||3||02/1987||11/2011|
|1.64||Quality Assurance Requirements for the Design of Nuclear Power plants
(Withdrawn -- See 56 FR 36175, 07/31/1991)
|1.65||Materials and Inspections for Reactor Vessel Closure Studs||1||04/2010|
|1.66||Nondestructive Examination of Tubular Products
(Withdrawn -- See 42 FR 54478, 10/6/1977)
|1.67||Installation of Overpressure Protection Devices
(Withdrawn -- See 48 FR 19101, 04/27/1983)
|1.68||Initial Test Programs for Water-Cooled Nuclear Power Plants||4||06/2013|
|1.68.1||Initial Test Program of Condensate and Feedwater Systems for Light-Water Reactors||2||09/2012|
|1.68.2||Initial Startup Test Program To Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants||2||04/2010|
|1.68.3||Preoperational Testing of Instrument and Control Air Systems||1||09/2012|
Concrete Radiation Shields and Generic Shield Testing for Nuclear Power Plants
Concrete Radiation Shields for Nuclear Power Plants
|1.70||Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)||3||11/1978||04/2009|
|1.71||Welder Qualification for Areas of Limited Accessibility||1||03/2007|
|1.72||Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin||2||11/1978||05/2009|
|1.73||Qualification Tests for Safety-Related Actuators in Nuclear Power Plants||1||10/2013|
|1.74||Quality Assurance Terms and Definitions
(Withdrawn -- See 54 FR 38919, 09/21/1989)
|1.75||Physical Independence of Electric Systems||3||02/2005|
|1.76||Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants||1||03/2007||08/2011|
|1.77||Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors||--||05/1974|
|1.78||Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release||1||12/2001||01/2012|
|1.79||Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors||2||10/2013|
|1.79.1||Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors||--||10/2013|
|1.80||Preoperational Testing of Instrument Air Systems
(Withdrawn -- See 47 FR 19258, 05/4/1982)