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Home NRC Library Document Collections Regulatory Guides (by Division) Division 1 - Power Reactors

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
Number		 Title Revision Number Publish
Date		 Additional
Information
1.61 Damping Values for Seismic Design of Nuclear Power Plants 2 12/2023  
1 03/2007 Periodic Review June 2022 – Revise

Periodic Review June 2018 – Revise

Periodic Review April 2015 – Revise
0 10/1973  
1.62 Manual Initiation of Protective Actions

1

 06/2010 Reviewed in 2017 – Issues identified for future consideration
0 10/1973  
1.63 Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants 3 02/1987 Reviewed in 2021 – No Issues identified
2 07/1978  
1 05/1977  
0 10/1973  
1.64 Quality Assurance Requirements for the Design of Nuclear Power plants
(Withdrawn -- See 56 FR 36175, 07/31/1991)		 W 07/1991  
2 06/1976  
1 02/1975  
1.65 Materials and Inspections for Reactor Vessel Closure Studs 1 04/2010 Reviewed in 2015 – No issues identified
0 10/1973  
1.66 Nondestructive Examination of Tubular Products
(Withdrawn -- See 42 FR 54478, 10/6/1977)		 W 10/1977  
0 10/1973  
1.67 Installation of Overpressure Protection Devices
(Withdrawn -- See 48 FR 19101, 04/27/1983)		 W 04/1983  
0 10/1973  
1.68 Initial Test Programs for Water-Cooled Nuclear Power Plants 4 06/2013 Periodic Review – April 2023 - Revise
3 03/2007  
2 08/1978  
1 01/1977  
0 11/1973  
1.68.1 Initial Test Program of Condensate and Feedwater Systems for Light-Water Reactors 2 09/2012 Periodic Review October 2022 Withdraw
1 01/1977  
0 12/1975  
1.68.2 Initial Startup Test Program To Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants 2 04/2010 Reviewed in 2015 – Issues identified for future consideration
1 07/1978  
0 01/1977  
1.68.3 Preoperational Testing of Instrument and Control Air Systems 1 09/2012  Periodic Review October 2022 Revise
0 04/1982  
1.69 Concrete Radiation Shields and Generic Shield Testing for Nuclear Power Plants 1 05/2009 Reviewed in 2014 – No issues identified
0 12/1973  
1.70 Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition) 3 11/1978 Reviewed in 2014 – Issues identified for future consideration
2 09/1975  
1 10/1972  
0 02/1972  
1.71 Welder Qualification for Areas of Limited Accessibility 1 03/2007 Periodic Review May 2022 – No issues identified
0 12/1973

Periodic Review March 2007
No Action
1.72 Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin 2 11/1978 Reviewed in 2014 – Issues identified for future consideration
1 01/1978  
0 12/1973  
1.73 Qualification Tests for Safety-Related Actuators in Nuclear Power Plants 2 01/2024  
1 10/2013  
0 01/1974  
1.74 Quality Assurance Terms and Definitions
(Withdrawn -- See 54 FR 38919, 09/21/1989)		 W 09/1989  
0 02/1974  
1.75 Criteria for Independence of Electrical Safety Systems 3 02/2005 Reviewed in 2016 – Issues identified for future consideration
2 09/1978  
1 01/1975  
0 02/1974  
1.76 Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants 1 03/2007 Reviewed in 2016 – Issues identified for future consideration
0 04/1974  
1.77 Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors
(Withdrawn -- See 85 FR 37118, 06/19/20) 		W 06/2020  
1.78 Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release 2 12/2021  
1 12/2001  
0 06/1974  
1.79 Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors 2 10/2013 Periodic Review – May 2023 -  Revise
1 09/1975  
0 06/1974  
1.79.1 Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors 0 10/2013 Periodic Review – May 2023 - Revise
1.80 Preoperational Testing of Instrument Air Systems
(Withdrawn -- See 47 FR 19258, 05/4/1982) 		W 05/1982  
0 06/1974  
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Page Last Reviewed/Updated Wednesday, April 3, 2024