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Power Reactors (Division 1): Regulatory Guides 1.221 - 1.240

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
Number
Issue
Date
Additional Information
1.221

Design-Basis Hurricane and Hurricane Missiles for Nuclear Power Plants
 

HISTORY
010/2011Periodic Review in 2016 – Reviewed with no issues identified
1.222

Conducting Periodic Testing for Breakaway Oxidation Behavior
 

HISTORY
  • 03/2014 – DG-1261, Proposed Revision 0
DG07/2026DG-1261 Issued
DG 10 CFR 50.46c
Rulemaking
SECY 16-0033
1.223

Testing for Postquench Ductility
 

HISTORY
  • 03/2014 – DG-1262, Proposed Revision 0
DG07/2026DG-1262
DG 10 CFR 50.46c
Rulemaking
SECY 16-0033
1.224

Establishing Analytical for Zirconium Based Alloy Cladding
 

HISTORY
  • 03/2014 – DG-1263, Proposed Revision 0
DG07/2026DG-1263
DG 10 CFR 50.46c
Rulemaking
SECY 16-0033
1.225An Approach for a Risk-Informed Evaluation Process Supporting Alternative Acceptance CriteriaDG07/2026DG-1426
1.226

Flexible Mitigation Strategies for Beyond-Design-Basis Events
 

HISTORY
006/2019 
1.227

Wide-Range Spent Fuel Pool Level Instrumentation
 

HISTORY
006/2019 
1.228

Integrated Response Capabilities for Beyond-Design Basis Events
 

HISTORY
  • 11/2015 – DG-1319, Proposed Revision 0
DG 08/2019 - Final Rule Federal Register Notice
1.229

Alternative Risk-Informed Approach for Addressing the Effects of Debris on Post Accident Long-Term Core Cooling
 

HISTORY
  • 04/2015 – DG-1322, Proposed Revision 0
DG 10 CFR 50.46c
Rulemaking
SECY 16-0033
1.230

Regulatory Guidance on the Alternate Pressurized Thermal Shock Rule
 

HISTORY
009/2018 
1.231

Acceptance of Commercial-Grade Design and Analysis Computer Programs Used in Safety-Related Applications for Nuclear Power Plants
 

HISTORY
012/2016 
1.232

Developing Principal Design Criteria for Non-Light Water Reactors
 

HISTORY
004/2018 
1.233

Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Methodology to Inform the Licensing Basis and Content of Applications for Licenses, Certifications, and Approvals for Non-Light Water Reactors
 

HISTORY
006/2020 
1.234

Evaluating Deviations and Reporting Defects and Noncompliance Under 10 CFR Part 21
 

HISTORY
103/2024 
004/2018 
1.235

Emergency Planning for Decommissioning Power Reactors
 

HISTORY
  • 02/2022 – DG-1346 Revision 1, Proposed Revision 0
  • 06/2020 – DG-1346, Proposed Revision 0
DG02/2022DG-1346 , Rev 1, Proposed Revision 0 for RG 1.235
1.236

Pressurized-Water Reactor Control Rod Ejection and Boiling-Water Reactor Control Rod Drop Accidents
 

HISTORY
006/2020 
1.237

Guidance for Changes During Construction for New Nuclear Power Plants Being Constructed Under a Combined License Referencing a Certified Design Under 10 CFR Part 52
 

HISTORY
DG07/2026DG-1461
002/2021 
1.238

Criteria for The Protection of Safety-Related (Class 1E) Power Systems and Equipment for Nuclear Power Plants  

HISTORY
001/2025 
1.239

Licensee Actions to Address Nonconservative Technical Specifications
 

HISTORY
011/2020 
1.240

Fresh and Spent Fuel Pool Criticality Analysis
 

HISTORY
003/2021 

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Page Last Reviewed/Updated Tuesday, August 11, 2026

Page Last Reviewed/Updated Tuesday, August 11, 2026