Power Reactors (Division 1): Regulatory Guides 1.41 - 1.60
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 | Issue | Additional Information |
|---|---|---|---|---|
1.41 | Preoperational Testing of Redundant On-Site Electric Power Systems To Verify Proper Load Group Assignments | |||
W | ||||
1.42 | Interim Licensing policy on as low as Practicable for Gaseous Radiodine Releases from Light-Water-Cooled Nuclear Power Reactors. | W | ||
1 | ||||
1.43 | Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components | 1 | ||
0 | ||||
1.44 | Control of the Processing and Use of Stainless Steel | 1 | ||
0 | ||||
1.45 | Guidance on Monitoring and Responding to Reactor Coolant System Leakage | 1 | ||
0 | ||||
1.46 | Protection Against Pipe Whip Inside Containment | W | ||
0 | ||||
1.47 | Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems | 1 | ||
0 | ||||
1.48 | Design Limit and Loading Combinations for Seismic Category I Fluid System Components | W | ||
0 | ||||
1.49 | Power Levels of Nuclear Power Plants | W | ||
1 | ||||
0 | ||||
1.50 | Control of Preheat Temperature for Welding of Low-Alloy Steel | 1 | ||
0 | ||||
1.51 | Inservice Inspection of ASME Code Class 2 and 3 Nuclear Power Plants components | W | ||
0 | ||||
1.52 | Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants | 4 | ||
3 | ||||
2 | ||||
1 | ||||
0 | ||||
1.53 | Application of the Single-Failure Criterion to Safety Systems | 2 | Reviewed in 2016 – Issues identified for future consideration | |
1 | ||||
0 | ||||
1.54 | Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants | 3 | ||
2 | ||||
1 | ||||
0 | ||||
1.55 | Concrete Placement in Category I Structures | W | ||
0 | ||||
1.56 | Maintenance of Water Purity in Boiling Water Reactors (for Comment) | W | ||
1 | ||||
0 | ||||
1.57 | Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components | 2 | ||
1 | ||||
0 | ||||
1.58 | Qualification of Nuclear Power Plant Inspection, Examination and Testing Personnel | W | ||
1 | ||||
1.59 | Design Basis Floods for Nuclear Power Plants | DG | DG-1290 Rev 1 | |
2 | ||||
1 | ||||
0 | ||||
1.60 | Design Response Spectra for Seismic Design of Nuclear Power Plants | 2 | ||
1 | ||||
0 |
Page Last Reviewed/Updated Tuesday, March 31, 2026
Page Last Reviewed/Updated Tuesday, March 31, 2026