Power Reactors (Division 1): Regulatory Guides 1.81 - 1.100
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 |
|---|---|---|---|---|
1.81 | Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants | 1 | ||
0 | 06/1974 | |||
1.82 | Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident | 5 | ||
4 | ||||
3 | ||||
2 | ||||
1 | ||||
0 | ||||
1.83 | Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes | W | ||
1 | ||||
0 | ||||
1.84 | Design, Fabrication, and Materials Code Case Acceptability, ASME Section III | 40 | ||
39 | ||||
38 | ||||
37 | ||||
36 | ||||
35 | ||||
34 | ||||
33 | ||||
32 | ||||
31 | ||||
30 | ||||
29 | ||||
28 | ||||
27 | ||||
26 | ||||
25 | ||||
24 | 06/1986 | |||
23 | ||||
22 | ||||
21 | 09/1983 | |||
20 | 11/1982 | |||
19 | 04/1982 | |||
18 | ||||
17 | ||||
16 | ||||
15 | ||||
14 | 11/1978 | |||
13 | ||||
12 | ||||
11 | ||||
10 | ||||
9 | ||||
8 | ||||
7 | ||||
6 | ||||
5 | ||||
4 | ||||
3 | ||||
2 | ||||
1 | ||||
0 | ||||
1.85 | Materials code case Acceptability - - ASME Section III, Division 1 | W | ||
31 | ||||
30 | ||||
27 | ||||
26 | ||||
23 | ||||
22 | ||||
21 | ||||
17 | ||||
16 | ||||
15 | ||||
14 | ||||
13 | ||||
12 | ||||
11 | ||||
10 | ||||
9 | ||||
8 | ||||
7 | ||||
6 | ||||
5 | ||||
4 | ||||
3 | ||||
2 | ||||
1 | ||||
0 | ||||
1.86 | Termination of Operating Licenses for Nuclear Reactors | W | ||
0 | ||||
1.87 | Acceptability of ASME Code Section III, Division 5, 'High Temperature Reactors'
| |||
3 | ||||
2 | ||||
1 | Periodic Review - February 2021 - Revise | |||
1.88 | Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records | W | ||
2 | ||||
1.89 | Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants | 2 | ||
1 | ||||
0 | ||||
1.90 | Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons | 2 | Reviewed in 2018 – Issues Identified for future consideration | |
1 | ||||
0 | ||||
1.91 | Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants | 3 | ||
2 | ||||
1 | ||||
0 | ||||
1.92 | Combining Modal Responses and Spatial Components in Seismic Response Analysis | 3 | Reviewed in 2018 – Issues identified for future consideration | |
2 | ||||
1 | ||||
0 | 12/1974 | |||
1.93 | Availability of Electric Power Sources | 1 | ||
0 | ||||
1.94 | Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants | W | ||
1 | ||||
0 | ||||
1.95 | Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release | W | ||
1 | ||||
1.96 | Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants | 1 | Periodic Review – August 2023 -Withdraw | |
0 | ||||
1.97 | Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants | 5 | ||
4 | ||||
3 | ||||
2 | ||||
1 | ||||
0 | ||||
1.98 | Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor (for Comment) | 0 | Reviewed in 2016 – Issues identified for future consideration | |
1.99 | Radiation Embrittlement of Reactor Vessel Materials | 2 | Periodic Review – November 2023 - Considerations | |
1 | ||||
0 | ||||
1.100 | Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants | 4 | ||
3 | ||||
2 | ||||
1 | ||||
0 |
Page Last Reviewed/Updated Friday, January 16, 2026
Page Last Reviewed/Updated Friday, January 16, 2026