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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 Division 1.

See NRC Regulatory Guides for more general information.

Reviewed (last column on table) means that the NRC has reviewed these guides and has determined that they are acceptable for continued use. The NRC encourages comments from stakeholders on any Regulatory Guide at any time. Comments received in this manner will be reviewed upon receipt, but will be fully evaluated during the next periodic review of the affect guides. Currently, Regulatory Guides are reviewed on a 5 year basis. In certain cases, a Regulatory Guide will be looked at before the 5 year period has passed.

Guide
Number
Title Rev. Publish
Date
Reviewed
1.41 Preoperational Testing of Redundant On-Site Electric Power Systems To Verify Proper Load Group Assignments -- 03/1973  
1.42 Interim Licensing policy on as low as Practicable for Gaseous Radiodine Releases from Light-Water-Cooled Nuclear Power Reactors.
(Withdrawn -- See 41 FR 11891, 03/22/1976)
W 03/1976  
1.43

Control of Stainless Steel Weld Cladding of Low-Alloy Steel Components

1 03/2011  
-- 05/1973
1.44 Control of the Use of Sensitized Stainless Steel 1 03/2011  
-- 05/1973
1.45 Guidance on Monitoring and Responding to Reactor Coolant System Leakage 1 05/2008  
-- 05/1973
1.46 Protection Againinst Pipe Whip Inside Containment
(Withdrawn -- See 50 FR 9732, 03/11/1985)
W 09/1985  
1.47 Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems 1 02/2010  
-- 05/1973
1.48 Design Limit and Loading Combinations for Seismic Category I Fluid System Components
(Withdrawn -- See 50 FR 9732, 03/11/1985)
W 03/1985  
1.49 Power Levels of Nuclear Power Plants
(Withdrawn -- See 72 FR 36737, 07/05/2007)
W 07/2007  
1 12/1973
1.50 Control of Preheat Temperature for Welding of Low-Alloy Steel 1 03/2011  
-- 05/1973
1.51 Inservice Inspection of ASME code Class 2 and 3 Nuclear Power Plants components
(Withdrawn -- See 40 FR 30540, 07/21/1975)
W 07/1975  
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 3 06/2001  
2 03/1978
1 07/1976
-- 06/1973
1.53 Application of the Single-Failure Criterion to Nuclear Power Plant Protection Systems 2 11/2003 03/2009
1 10/2003
-- 06/1973
1.54 Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants 2 10/2010  
1 07/2000
-- 06/1973
1.55 Concrete Placement in Category I Structures
(Withdrawn -- See 46 FR 37579, 07/21/1981)
W 07/1981  
1.56 Maintenance of Water Purity in Boiling Water Reactors (for Comment)
(Withdrawn -- See 75 FR 7526, 02/19/2010)
W 02/2010  
1 07/1978
-- 06/1973
1.57 Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components 1 03/2007  
-- 06/1973
1.58 Qualification of Nuclear Power Plant Inspection, Examination and Testing Personnel
(Withdrawn -- See 56 FR 36175, 07/31/1991)
W 07/1991
1 09/1980
1.59 Design Basis Floods for Nuclear Power Plants 2 08/1977  
1 04/1976
-- 08/1973
1.60 Design Response Spectra for Seismic Design of Nuclear Power Plants 1 12/1973 10/2010
-- 10/1973

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Page Last Reviewed/Updated Monday, September 24, 2012