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 | Title | Revision Number | Issue Date | Additional Information |
|---|---|---|---|---|
| 1.181 | Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e) HISTORY
| 0 | 09/1999 | Reviewed in 2019 – Revise |
| 1.182 | Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants HISTORY
| W | 11/2012 | |
| 0 | 05/2000 | |||
| 1.183 | Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors | DG | 07/2026 | DG-1425 |
| DG | 7/2026 | DG-1425 was issued | ||
| 1 | 10/2023 | |||
| 0 | 07/2000 | Reviewed in 2018 – Revise | ||
| 1.184 | Decommissioning of Nuclear Power Reactors | DG | 02/2022 | DG-1347, rev 1, proposed rev 2 of RG 1.184 |
| 1 | 10/2013 | |||
| 0 | 07/2000 | |||
| 1.185 | Standard Format and Content for Post-Shutdown Decommissioning Activities Report | DG | 02/2022 | DG-1349, rev 1, proposed rev 2 of RG 1.185 |
| 1 | 06/2013 | |||
| 0 | 07/2000 | |||
| 1.186 | Guidance and Examples for Identifying 10 CFR 50.2 Design Bases HISTORY
| 0 | 12/2000 | Periodic 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 | DG | 07/2026 | DG-1466 |
| 3 | 06/2021 | |||
| 2 | 06/2020 | |||
| 1 | 05/2019 | |||
| 0 | 11/2000 | Periodic Review April 2011 No Action | ||
| 1.188 | Standard Format and Content for Applications To Renew Nuclear Power Plant Operating Licenses HISTORY
| 2 | 04/2020 | |
| 1 | 09/2005 | |||
| 0 | 07/2001 | |||
| 1.189 | Fire Protection for Nuclear Power Plants HISTORY
| 5 | 10/2023 | Administrative Change |
| 4 | 05/2021 | |||
| 3 | 02/2018 | Periodic Review – November 2017 - Revise | ||
| 2 | 10/2009 | Periodic Review – December 2014 -Considerations | ||
| 1 | 03/2007 | |||
| 0 | 04/2001 | |||
| 1.190 | Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence | 0 | 03/2001 | Periodic 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 HISTORY
| 1 | 01/2021 | |
| 0 | 05/2001 | |||
| 1.192 | Operation and Maintenance Code Case Acceptability, ASME OM Code | DG | 02/2026 | Issued DG-1448: Federal Register Notice |
| 5 | 03/2024 | 07/2024: Final Rule Federal Register Notice | ||
| 4 | 12/2021 | 03/2022: Final Rule Federal Register Noticehttps://www.federalregister.gov/documents/2024/07/17/2024-15288/american-society-of-mechanical-engineers-code-cases-and-update-frequency | ||
| 3 | 10/2019 | 03/2020: Final Rule Federal Register Notice | ||
| 2 | 03/2017 | 01/2018: Final Rule Federal Register Notice | ||
| 1 | 10/2014 | |||
| 0 | 06/2003 | |||
| 1.193 | ASME Code Cases Not Approved for Use HISTORY
| 8 | 03/2024 | 07/2024: Final Rule Federal Register Notice |
| 7 | 12/2021 | 03/2022: Final Rule Federal Register Notice | ||
| 6 | 10/2019 | 03/2020: Final Rule Federal Register Notice | ||
| 5 | 08/2017 | 01/2018: Final Rule Federal Register Notice | ||
| 4 | 10/2014 | |||
| 3 | 10/2010 | |||
| 2 | 10/2007 | |||
| 1 | 08/2005 | |||
| 0 | 06/2003 | |||
| 1.194 | Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants HISTORY
| 0 | 06/2003 | Reviewed 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 HISTORY
| 0 | 05/2003 | Periodic Review in 2026 – Reviewed with issues identified for future consideration Periodic Review in 2016 – Reviewed with no issues identified |
| 1.196 | Control Room Habitability at Light-Water Nuclear Power Reactors HISTORY
| 1 | 01/2007 | Periodic Review – August 2023 - Considerations |
| 0 | 05/2003 | Periodic Review - August 2013 – Considerations | ||
| 1.197 | Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors HISTORY
| 0 | 05/2003 | Periodic 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 HISTORY
| 0 | 11/2003 | Reviewed February 2025 - Revise |
| 1.199 | Anchoring Components and Structural Supports in Concrete HISTORY
| 1 | 04/2020 | |
| 0 | 11/2003 | |||
| 1.200 | Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities HISTORY
| 3 | 12/2020 | |
| 2 | 03/2009 | Public Meeting Slides July 2008 | ||
| 1 | 01/2007 | |||
| 0 | 02/2004 |
Page Last Reviewed/Updated Tuesday, August 11, 2026
Page Last Reviewed/Updated Tuesday, August 11, 2026