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Power Reactors (Division 1): Regulatory Guides 1.181 - 1.200

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
1.181

Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)

009/1999Reviewed in 2019 – Revise
1.182

Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants
(Withdrawn – See 77 FR 70846, 11/27/2012)

W11/2012 
005/2000 
1.183

Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors

110/2023 
007/2000Reviewed in 2018 – Revise
1.184

Decommissioning of Nuclear Power Reactors

DG02/2022DG-1347, rev 1, proposed rev 2 of RG 1.184
110/2013 
007/2000 
1.185

Standard Format and Content for Post-Shutdown Decommissioning Activities Report

DG02/2022DG-1349, rev 1, proposed rev 2 of RG 1.185
106/2013 
007/2000 
1.186

Guidance and Examples for Identifying 10 CFR 50.2 Design Bases

012/2000Periodic Review in 2026 – Reviewed with no issues identified 

Periodic Review in 2017 – Reviewed with no issues identified
1.187

Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments

306/2021 
206/2020 
105/2019 
011/2000Periodic Review
April 2011
No Action
1.188

Standard Format and Content for Applications To Renew Nuclear Power Plant Operating Licenses

204/2020 
109/2005 
007/2001 
1.189

Fire Protection for Nuclear Power Plants

510/2023Administrative Change
405/2021 
302/2018Periodic Review – November 2017
- Revise
210/2009Periodic Review – December 2014
-Considerations
103/2007 
004/2001 
1.190

Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence

003/2001Periodic Review 06/2023 –
Considerations
 
Periodic Review 05/2013 – Considerations
 
Periodic Review 04/2006 – No Action
1.191

Fire Protection Program for Nuclear Power Plants During Decommissioning and Permanent Shutdown

101/2021 
005/2001 
1.192

Operation and Maintenance Code Case Acceptability, ASME OM Code

503/202407/2024: Final Rule Federal Register Notice
412/202103/2022: Final Rule Federal Register Notice
310/201903/2020: Final Rule Federal Register Notice
203/201701/2018: Final Rule Federal Register Notice
110/2014 
006/2003 
1.193

ASME Code Cases Not Approved for Use

803/202407/2024: Final Rule Federal Register Notice
712/202103/2022: Final Rule Federal Register Notice
610/201903/2020: Final Rule Federal Register Notice
508/201701/2018: Final Rule Federal Register Notice
410/2014 
310/2010 
210/2007 
108/2005 
006/2003 
1.194

Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants

006/2003Reviewed in 2015 – Issues identified with future consideration
1.195

Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors

005/2003Reviewed in 2016 – No issues identified
1.196

Control Room Habitability at Light-Water Nuclear Power Reactors

101/2007Periodic Review – August 2023 - Considerations
005/2003Periodic Review - August 2013 – Considerations
1.197

Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors

005/2003Periodic Review – June 2025 - Reviewed with Issues Identified for Future Consideration

Reviewed in 2015 – No issues identified
1.198

Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites

011/2003Reviewed February 2025 - Revise
1.199

Anchoring Components and Structural Supports in Concrete

104/2020 
011/2003 
1.200

Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities

312/2020 
203/2009Public Meeting Slides
July 2008
101/2007 
002/2004 

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Page Last Reviewed/Updated Tuesday, June 02, 2026

Page Last Reviewed/Updated Tuesday, June 02, 2026