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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
TitleRevision NumberPublish
Date
Additional
Information
1.61

Damping Values for Seismic Design of Nuclear Power Plants

212/2023 
103/2007Periodic Review June 2022 – Revise

Periodic Review June 2018 – Revise

Periodic Review April 2015 – Revise
010/1973 
1.62

Manual Initiation of Protective Actions

1

06/2010Reviewed in 2017 – Issues identified for future consideration
010/1973 
1.63

Electric Penetration Assemblies in Containment Structures for Nuclear Power Plants

302/1987Reviewed in 2025 - Revise
207/1978 
105/1977 
010/1973 
1.64Quality Assurance Requirements for the Design of Nuclear Power plants
(Withdrawn -- See 56 FR 36175, 07/31/1991)
W07/1991 
206/1976 
102/1975 
1.65

Materials and Inspections for Reactor Vessel Closure Studs

104/2010Reviewed in 2015 – No issues identified
010/1973 
1.66Nondestructive Examination of Tubular Products
(Withdrawn -- See 42 FR 54478, 10/6/1977)
W10/1977 
010/1973 
1.67Installation of Overpressure Protection Devices
(Withdrawn -- See 48 FR 19101, 04/27/1983)
W04/1983 
010/1973 
1.68

Initial Test Programs for Water-Cooled Nuclear Power Plants

406/2013Periodic Review – April 2023 - Revise
303/2007 
208/1978 
101/1977 
011/1973 
1.68.1

Initial Test Program of Condensate and Feedwater Systems for Light-Water Reactors

209/2012Periodic Review October 2022 Withdraw
101/1977 
012/1975 
1.68.2

Initial Startup Test Program To Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants

204/2010Periodic Review in 2026 – Reviewed with issues identified for future consideration 

Periodic Review in 2015 – Reviewed with issues identified for future consideration
107/1978 
001/1977 
1.68.3

Preoperational Testing of Instrument and Control Air Systems

109/2012Periodic Review October 2022 Revise
004/1982 
1.69

Concrete Radiation Shields and Generic Shield Testing for Nuclear Power Plants

105/2009Periodic Review July 2025 – Revise

Reviewed in 2014 – No issues identified
012/1973 
1.70

Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants (LWR Edition)

311/1978

Periodic Review in 2025 - Reviewed with issues identified for future consideration

Periodic Review in 2014 - Reviewed with issues identified for future consideration

209/1975 
110/1972 
002/1972 
1.71

Welder Qualification for Areas of Limited Accessibility

103/2007Periodic Review May 2022 – No issues identified
012/1973

Periodic Review March 2007
No Action

1.72Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin211/1978Periodic Review – May 2024
- Considerations

Reviewed in 2014 – Issues identified for future consideration

Periodic Review – May 2009
-No Action
101/1978 
012/1973 
1.73

Qualification Tests for Safety-Related Actuators in Nuclear Power Plants

201/2024 
110/2013 
001/1974 
1.74Quality Assurance Terms and Definitions
(Withdrawn -- See 54 FR 38919, 09/21/1989)
W09/1989 
002/1974 
1.75

Criteria for Independence of Electrical Safety Systems

302/2005Reviewed in 2016 – Issues identified for future consideration
209/1978 
101/1975 
002/1974 
1.76

Design-Basis Tornado and Tornado Missiles for Nuclear Power Plants

103/2007Reviewed in 2016 – Issues identified for future consideration
004/1974 
1.77

Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors
(Withdrawn -- See 85 FR 37118, 06/19/20)

W06/2020 
1.78

Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release

212/2021 
112/2001 
006/1974 
1.79

Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors

210/2013Periodic Review – May 2023 -  Revise
109/1975 
006/1974 
1.79.1

Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors

010/2013Periodic Review – May 2023 - Revise
1.80

Preoperational Testing of Instrument Air Systems
(Withdrawn -- See 47 FR 19258, 05/4/1982)

W05/1982 
006/1974 

Page Last Reviewed/Updated Thursday, May 21, 2026

Page Last Reviewed/Updated Thursday, May 21, 2026