Power Reactors (Division 1): Regulatory Guides 1.161 - 1.180
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 Date | Issue | Additional Information |
|---|---|---|---|---|
1.161 | Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft-Lb | 0 | Reviewed in 2014 – No issues identified | |
1.162 | Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels | 0 | Periodic review in 2025 – Reviewed with no issues identified Periodic review in 2014 – No issues identified | |
1.163 | Performance-Based Containment Leak-Test Program | 1 | ||
0 | Periodic Review | |||
1.164 | Dedication of Commercial-Grade Items for Use in Nuclear Power Plants | 1 | ||
0 | ||||
1.165 | Identification and Characterization of Seismic Sources and Determination of Safe Shutdown Earthquake Ground Motion | W | ||
0 | ||||
1.166 | Pre-Earthquake Planning, Shutdown, and Restart of a Nuclear Power Plant Following an Earthquake | 1 | ||
0 | ||||
1.167 | Restart of a Nuclear Power Plant Shut Down by a Seismic Event | W | ||
0 | ||||
1.168 | Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants | 2 | ||
1 | ||||
0 | ||||
1.169 | Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants | 1 | ||
0 | ||||
1.170 | Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants | 1 | ||
0 | ||||
1.171 | Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants | 1 | ||
0 | ||||
1.172 | Software Requirement Specifications for Digital Computer Software and Complex Electronics Used in Safety Systems of Nuclear Power Plants | 1 | ||
0 | ||||
1.173 | Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants | 1 | ||
0 | ||||
1.174 | An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis | |||
3 | ||||
2 | ||||
1 | ||||
0 | ||||
1.175 | Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing | 1 | ||
0 | ||||
1.176 | An Approach for Plant-Specific, Risk-Informed Decisionmaking: Graded Quality Assurance | W | ||
0 | ||||
1.177 | Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications | 2 | ||
1 | ||||
0 | ||||
1.178 | An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping | 2 | ||
1 | ||||
0 | ||||
1.179 | Standard Format and Content of License Termination Plans for Nuclear Power Reactors | 2 | ||
1 | ||||
0 | ||||
1.180 | Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems | 2 | ||
1 | ||||
0 |
Page Last Reviewed/Updated Wednesday, February 18, 2026
Page Last Reviewed/Updated Wednesday, February 18, 2026