Spotlight
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 | Title | Revision | Issue | Additional Information |
|---|---|---|---|---|
1.181 | Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e) | 0 | ||
1.182 | Assessing and Managing Risk Before Maintenance Activities at Nuclear Power Plants | W | ||
0 | ||||
1.183 | Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors | 1 | ||
0 | ||||
1.184 | Decommissioning of Nuclear Power Reactors | 1 | ||
0 | ||||
1.185 | Standard Format and Content for Post-Shutdown Decommissioning Activities Report | 1 | ||
0 | ||||
1.186 | Guidance and Examples for Identifying 10 CFR 50.2 Design Bases | 0 | ||
1.187 | Guidance for Implementation of 10 CFR 50.59, Changes, Tests, and Experiments | 3 | ||
2 | ||||
1 | ||||
0 | Periodic Review | |||
1.188 | Standard Format and Content for Applications To Renew Nuclear Power Plant Operating Licenses | 2 | ||
1 | ||||
0 | ||||
1.189 | Fire Protection for Nuclear Power Plants | 5 | Administrative Change | |
4 | ||||
3 | ||||
2 | ||||
1 | ||||
0 | ||||
1.190 | Calculational and Dosimetry Methods for Determining Pressure Vessel Neutron Fluence | 0 | Periodic Review 06/2023 – | |
1.191 | Fire Protection Program for Nuclear Power Plants During Decommissioning and Permanent Shutdown | 1 | ||
0 | ||||
1.192 | Operation and Maintenance Code Case Acceptability, ASME OM Code | 5 | ||
4 | ||||
3 | ||||
2 | ||||
1 | ||||
0 | ||||
1.193 | ASME Code Cases Not Approved for Use | 8 | ||
7 | ||||
6 | ||||
5 | ||||
4 | ||||
3 | ||||
2 | ||||
1 | ||||
0 | ||||
1.194 | Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants | 0 | 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 | 0 | ||
1.196 | Control Room Habitability at Light-Water Nuclear Power Reactors | 1 | ||
0 | ||||
1.197 | Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors | 0 | Periodic Review – June 2025 - Reviewed with Issues Identified for Future Consideration | |
1.198 | Procedures and Criteria for Assessing Seismic Soil Liquefaction at Nuclear Power Plant Sites | 0 | ||
1.199 | Anchoring Components and Structural Supports in Concrete | 1 | ||
0 | ||||
1.200 | Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities | 3 | ||
2 | ||||
1 | ||||
0 |
Page Last Reviewed/Updated Friday, January 16, 2026
Page Last Reviewed/Updated Friday, January 16, 2026