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Power Reactors (Division 1): Regulatory Guides 1.1 - 1.20

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 dates (the last column in the table) are when the staff completed a periodic review of the associated guide. Regulatory Guides are reviewed about every 5 years, although in some cases a guide will reviewed before the normal 5 year period. 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.

The NRC encourages suggestions from stakeholders regarding any Regulatory Guide or development of new guides at any time. Suggestions received in this manner will be reviewed upon receipt, but will typically be fully evaluated during the next periodic review of the affect guides.

Guide
Number
Title Rev. Publish
Date
Reviewed
1.1 Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps (Safety Guide 1) -- 11/1970  
1.2 Thermal Shock to Reactor Pressure Vessels (Safety Guide 2)
(Withdrawn -- See 56 FR 36175, 07/31/1991)
W 07/1991  
-- 11/1970  
1.3 Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors 2 06/1974 10/2010
1 06/1973  
-- 11/1970  
1.4 Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors 2 06/1974 10/2010
1 06/1973  
-- 11/1970  
1.5 Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors (Safety Guide 5) -- 03/1971 10/2010
1.6 Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems (Safety Guide 6) -- 03/1971 03/2014
1.7 Control of Combustible Gas Concentrations in Containment 3 03/2007  
2 11/1978  
1 09/1976  
-- 03/1971  
1.8 Qualification and Training of Personnel for Nuclear Power Plants 3 05/2000 09/2014
2 04/1987  
1-R 05/1977  
1 09/1975  
-- 03/1971  
1.9 Application and Testing of Safety-Related Diesel Generators in Nuclear Power Plants 4 03/2007 03/2014
3 07/1993  
2 12/1979  
1 11/1978  
-- 08/1971  
1.10 Mechanical (Cadweld) Splices in Reinforcing Bars of Category I Concrete Structures
(Withdrawn -- See 46 FR 37579, 07/21/1981)
W 07/1981  
1 01/1973  
1.11 Instrument Lines Penetrating Primary Reactor Containment (Safety Guide 11) 1 03/2010  
Supp 02/1972  
-- 03/1971  
1.12 Nuclear Power Plant Instrumentation for Earthquakes 2 03/1997  
1 04/1974  
-- 03/1971  
1.13 Spent Fuel Storage Facility Design Basis 2 03/2007  
1 12/1975  
-- 03/1971  
1.14 Reactor Coolant Pump Flywheel Integrity 1 08/1975 04/2013
01/2006
-- 10/1971  
1.15 Testing of Reinforcing Bars for Category I Concrete Structures
(Withdrawn -- See 46 FR 37579, 07/21/1981)
W 07/1981  
1 12/1972  
1.16 Reporting of Operating Information -- Appendix A Technical Specifications (for Comment)
(Withdrawn -- See 74 FR 40244, 08/11/2009)
W 08/2009  
4 08/1975  
3 01/1975  
2 09/1974  
1 10/1973  
-- 10/1971  
1.17 Protection of Nuclear Power Plants Against Industrial Sabotage
(Withdrawn -- See 56 FR 30777, 07/05/1991)
W 07/1991  
1 06/1973  
-- 10/1971  
1.18 Structural Acceptance Test for Concrete Primary Reactor
(Withdrawn -- See 46 FR 37579, 07/21/1981)
W 07/1981  
1 12/1972  
-- 10/1971  
1.19 Nondestructive Examination of Primary Containment Liner Welds
(Withdrawn -- See 46 FR 37579, 07/21/1981)
W 07/1981  
1 08/1972  
-- 12/1971  
1.20 Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing 3 03/2007 03/2013
2 05/1976  
1 06/1975  
-- 12/1971  

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Page Last Reviewed/Updated Thursday, November 06, 2014