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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 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	Issue Date	Additional Information
1.1	Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal System Pumps (Safety Guide 1) (Withdrawn -- See 80 FR 24293, 04/30/2015)	W	04/2015
1.1		0	11/1970
1.2	Thermal Shock to Reactor Pressure Vessels (Safety Guide 2) (Withdrawn -- See 56 FR 36175, 07/31/1991)	W	07/1991
1.2		0	11/1970
1.3	Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors (Withdrawn – See 81 FR 88710, 12/08/2016) + HISTORY - HISTORY 03/2016 – Periodic Review of Revision 2 – Withdraw 10/2010 – Periodic Review of Revision 2 - No Issues Identified Guidance from RG 1.3 has been updated and incorporated into RG 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," and RG 1.195, "Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors"5	W	12/2016
		2	06/1974
		1	06/1973
		0	11/1970
1.4	Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors (Withdrawn – See 81 FR 88710, 12/08/2016) + HISTORY - HISTORY 03/2016 – Periodic Review of Revision 2 – Withdraw 10/2010 – Periodic Review of Revision – No Issues Identified Guidance from RG 1.4 has been updated and incorporated into RG 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," and RG 1.195, "Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors"	W	12/2016
		2	06/1974
		1	06/1973
		0	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) (Withdrawn – See 81 FR 88710, 12/08/2016) + HISTORY - HISTORY 03/2016 – Periodic Review of Revision 0 – Withdraw 10/2010 – Periodic Review of Revision 0 – No Issues Identified Guidance from RG 1.5 has been updated and incorporated into RG 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," and RG 1.195, "Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors"	W	12/2016
1.5		0	03/1971
1.6	Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems (Safety Guide 6)	0	03/1971	Reviewed in 2014 – No Issues Identified
1.7	Control of Combustible Gas Concentrations in Containment + HISTORY - HISTORY 08/2002 – DG-1117, Proposed Revision 3 Prior to the issuance of DG-1117, RG 1.7 was entitled "Control of Combustible Gas Concentrations in Containment Following a Loss-of-Coolant Accident," to reflect its narrower original scope	3	03/2007	Periodic Review – May 2023 – Revise Reviewed in 2013 – Reviewed with issues identified for future consideration
		2	11/1978
		1	09/1976
		0	03/1971
1.8	Qualification and Training of Personnel for Nuclear Power Plants + HISTORY - HISTORY 02/2018 – DG-1329, Proposed Revision 4 09/2014 – Periodic Review of Revision 3 – Revise 03/1999 – DG-1084, Second Proposed Revision 3 09/1996 – DG-1012, First Proposed Revision 3 01/1985 – Draft OL 403-5, Third Proposed Revision 2 09/1980 – Draft RS 807-5, Second Proposed Revision 2 02/1979 – Draft RS 807-5, First Proposed Revision 2	4	06/2019
		3	05/2000
		2	04/1987
		1-R	05/1977
		1	09/1975
		0	03/1971
1.9	Application and Testing of Safety-Related Diesel Generators in Nuclear Power Plants + HISTORY - HISTORY 11/2006 – DG-1172, Proposed Revision 4 Prior to the issuance of DG-1172, RG 1.9 was entitled "Selection, Design, Qualification, and Testing of Emergency Diesel Generator Units Used as Class 1E Onsite Electric Power Systems at Nuclear Power Plants" 04/1992 – DG-1021, Second Proposed Revision 3 11/1988 – Draft RS 802-5, First Proposed Revision 3	DG	01/2021	DG-1303, Proposed Revision 5
		4	03/2007	Periodic Review – February 2024 – Revise Periodic Review – February 2014 – No Action
		3	07/1993
		2	12/1979
		1	11/1978
		0	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
1.10		1	01/1973
1.11	Instrument Lines Penetrating Primary Reactor Containment + HISTORY - HISTORY 09/2009 – DG-1225, Proposed Revision 1 Prior to the issuance of Revision 1, RG 1.11 was entitled "Instrument Lines Penetrating Primary Reactor Containment (Safety Guide 11) Supplement to Safety Guide 11, Backfitting Considerations"	1	03/2010	Reviewed in 2015 – No Issues Identified
		Supp	02/1972
		0	03/1971
1.12	Nuclear Power Plant Instrumentation for Earthquakes + HISTORY - HISTORY 09/2016 – DG-1332, Proposed Revision 3 04/2015 – Periodic Review on Revision 2 – Revise 02/1995 – DG-1033, Third Proposed Revision 2 11/1992 – DG-1016, Second Proposed Revision 2 07/1981 – Draft MS 140-5, First Proposed Revision 2	3	11/2017
		2	03/1997
		1	04/1974
		0	03/1971
1.13	Spent Fuel Storage Facility Design Basis + HISTORY - HISTORY 10/2013 – Periodic Review of Revision 2 – No Issues Identified 10/2006 – DG-1162, Second Proposed Revision 2 12/1981 – Draft CE 913-5, First Proposed Revision 2 Revision 1 was issued for public comment on 12/1975	2	03/2007	Reviewed in 2015 – No Issues Identified
		1	12/1975
		0	03/1971
1.14	Reactor Coolant Pump Flywheel Integrity + HISTORY - HISTORY 01/2006 – Periodic Review of Revision 1 – No Issues Identified	1	08/1975	Periodic Review – June 2023 - Considerations Reviewed in 2013 – Reviewed with issues identified for future consideration
1.14		0	10/1971
1.15	Testing of Reinforcing Bars for Category I Concrete Structures (Withdrawn -- See 46 FR 37579, 07/21/1981)	W	07/1981
1.15		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
		0	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
		0	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
		0	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
		0	12/1971
1.20	Comprehensive Vibration Assessment Program for Reactor Internals During Preoperational and Initial Startup Testing + HISTORY - HISTORY 07/2015 – DG-1323, Proposed Revision 4 03/2013 – Periodic Review of Revision 3 – No Issues Identified 11/2006 – DG-1163, Proposed Revision 3	4	02/2017
		3	03/2007
		2	05/1976
		1	06/1975
		0	12/1971

Page Last Reviewed/Updated Wednesday, April 3, 2024