Spotlight
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 Public Comment.
See NRC Regulatory Guides for more general information.
Regulatory Guides are reviewed about every 10 years, although a guide may be reviewed more frequently if the staff believes an emerging issue affects the guide. 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.
Guide | Title | Revision Number | Publish | Additional |
|---|---|---|---|---|
1.61 | Damping Values for Seismic Design of Nuclear Power Plants | 2 | ||
1 | Periodic Review June 2022 – Revise | |||
0 | ||||
1.62 | Manual Initiation of Protective Actions | 1 | Reviewed in 2017 – Issues identified for future consideration | |
0 | ||||
1.63 | Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants | 3 | ||
2 | ||||
1 | ||||
0 | ||||
1.64 | Quality Assurance Requirements for the Design of Nuclear Power plants | W | ||
2 | ||||
1 | ||||
1.65 | Materials and Inspections for Reactor Vessel Closure Studs | 1 | ||
0 | ||||
1.66 | Nondestructive Examination of Tubular Products | W | ||
0 | ||||
1.67 | Installation of Overpressure Protection Devices | W | ||
0 | ||||
1.68 | Initial Test Programs for Water-Cooled Nuclear Power Plants | 4 | ||
3 | ||||
2 | ||||
1 | 01/1977 | |||
0 | ||||
1.68.1 | Initial Test Program of Condensate and Feedwater Systems for Light-Water Reactors | 2 | ||
1 | ||||
0 | ||||
1.68.2 | Initial Startup Test Program To Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants | 2 | Reviewed in 2015 – Issues identified for future consideration | |
1 | ||||
0 | 01/1977 | |||
1.68.3 | Preoperational Testing of Instrument and Control Air Systems | 1 | ||
0 | ||||
1.69 | Concrete Radiation Shields and Generic Shield Testing for Nuclear Power Plants | 1 | Periodic Review July 2025 – Revise | |
0 | ||||
1.70 | Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition) | 3 | Reviewed in 2014 – Issues identified for future consideration | |
2 | ||||
1 | ||||
0 | ||||
1.71 | Welder Qualification for Areas of Limited Accessibility | 1 | ||
0 | Periodic Review March 2007 | |||
1.72 | Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin | 2 | Periodic Review – May 2024 | |
1 | 01/1978 | |||
0 | ||||
1.73 | Qualification Tests for Safety-Related Actuators in Nuclear Power Plants | 2 | ||
1 | ||||
0 | ||||
1.74 | Quality Assurance Terms and Definitions | W | ||
0 | ||||
1.75 | Criteria for Independence of Electrical Safety Systems | 3 | Reviewed in 2016 – Issues identified for future consideration | |
2 | ||||
1 | ||||
0 | 02/1974 | |||
1.76 | Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants | 1 | Reviewed in 2016 – Issues identified for future consideration | |
0 | ||||
1.77 | Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors | W | ||
1.78 | Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release | 2 | ||
1 | ||||
0 | ||||
1.79 | Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors | 2 | ||
1 | ||||
0 | ||||
1.79.1 | Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors | 0 | ||
1.80 | Preoperational Testing of Instrument Air Systems | W | ||
0 |
Page Last Reviewed/Updated Tuesday, December 09, 2025
Page Last Reviewed/Updated Tuesday, December 09, 2025