Spotlight
Power Reactors (Division 1): Regulatory Guides 1.141 - 1.160
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 Number | Issue | Additional Information |
|---|---|---|---|---|
1.141 | Containment Isolation Provisions for Fluid Systems | 1 | Reviewed in 2015 – Issues identified for future consideration | |
0 | ||||
1.142 | Safety-Related Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments) | 3 | ||
2 | ||||
1 | ||||
0 | ||||
1.143 | Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants | 2 | Reviewed in 2020 – Reviewed with issues identified for future consideration | |
1 | ||||
0 | ||||
1.144 | Auditing of Quality Assurance Programs for Nuclear Power Plants | W | ||
1 | ||||
1.145 | Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants | 1 | Reviewed in 2014 – Issues identified for future consideration | |
0 | ||||
1.146 | Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants | W | ||
0 | ||||
1.147 | Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1 | 21 | ||
20 | ||||
19 | ||||
18 | ||||
17 | ||||
16 | ||||
15 | ||||
14 | ||||
13-R | ||||
13 | ||||
12 | ||||
11 | ||||
10 | ||||
9 | ||||
8 | ||||
7 | ||||
6 | ||||
5 | ||||
4 | ||||
3 | ||||
2 | 06/1983 | |||
1 | ||||
0 | ||||
1.148 | Functional Specification for Active Valve Assemblies in Systems Important to Safety in Nuclear Power Plants | W | ||
0 | ||||
1.149 | Nuclear Power Plant Simulation Facilities for Use in Operator Training, License Examinations, and Applicant Experience Requirements | 4 | ||
3 | ||||
2 | ||||
1 | ||||
0 | ||||
1.150 | Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations | W | ||
1 | ||||
0 | ||||
1.151 | Instrument Sensing Lines | 2 | ||
1 | ||||
0 | ||||
1.152 | Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants | 4 | ||
3 | Periodic Review 05/2019 – Revise | |||
2 | ||||
1 | ||||
0 | ||||
1.153 | Criteria for Safety Systems (12/85) | DG | ||
0 | ||||
1 | Reviewed in 2017 – Issues identified for future consideration | |||
1.154 | Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors | W | ||
0 | ||||
1.155 | Station Blackout | 0 | Reviewed in 2015 – Issues identified for future consideration | |
1.156 | Qualification of Connection Assemblies for Nuclear Power Plants | 2 | ||
1 | ||||
0 | ||||
1.157 | Best-Estimate Calculations of Emergency Core Cooling System Performance | 0 | Reviewed in 2013 – Issues Identified for future consideration | |
1.158 | Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants | 1 | ||
0 | ||||
1.159 | Assuring the Availability of Funds for Decommissioning Nuclear Reactors | 2 | ||
1 | ||||
0 | ||||
1.160 | Monitoring the Effectiveness of Maintenance at Nuclear Power Plants | 4 | ||
3 | ||||
2 | ||||
1 | ||||
0 |
Page Last Reviewed/Updated Wednesday, December 03, 2025
Page Last Reviewed/Updated Wednesday, December 03, 2025