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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
Number
TitleRevision NumberIssue
Date
Additional Information
1.81

Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants

101/1975Reviewed in 2019 – No issues identified
006/1974 
1.82

Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident

508/2022 
403/201201/2015 – PR – Revise
311/2003 
205/1996 
111/1985 
006/1974 
1.83Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes
(Withdrawn -- See 74 FR 58324, 11/12/2009)
W11/2009 
107/1975 
007/1974 
1.84

Design, Fabrication, and Materials Code Case Acceptability, ASME Section III

4003/202407/2024: Final Rule Federal Register Notice
3912/202103/2022: Final Rule Federal Register Notice
3810/201903/2020: Final Rule Federal Register Notice
3703/201701/2018: Final Rule Federal Register Notice
3608/2014 
3510/2010 
3410/2007 
3308/2005 
3206/2003 
3105/1999 
3010/1994 
2907/1993 
2804/1992 
2711/1990 
2607/1989 
2505/1998 
2406/1986 
2309/1985 
2207/1984 
2109/1983 
2011/1982 
1904/1982 
1808/1981 
1712/1980 
1605/1980 
1505/1979 
1411/1978 
1307/1978 
1203/1978 
1111/1977 
1008/1977 
903/1977 
811/1976 
708/1976 
605/1976 
503/1976 
411/1975 
309/1975 
206/1975 
104/1975 
006/1974 
1.85

Materials code case Acceptability - - ASME Section III, Division 1
(Withdrawn See -- 69 FR 34202 06/18/2004)

W06/2004 
3105/1999 
3010/1994 
2711/1990 
2607/1989 
2309/1985 
2207/1984 
2109/1983 
1712/1980 
1605/1980 
1505/1979 
1411/1978 
1307/1978 
1203/1978 
1111/1977 
1008/1977 
903/1977 
811/1976 
708/1976 
605/1976 
502/1976 
411/1975 
309/1975 
206/1975 
104/1975 
006/1974 
1.86

Termination of Operating Licenses for Nuclear Reactors
(Withdrawn -- See 81 FR 53507, 08/12/2016)

W08/2016 
006/1974 
1.87

Acceptability of ASME Code Section III, Division 5, 'High Temperature Reactors'


Supplement to ASME Section III Code Cases 1592, 1593, 1594, 1595, and 1596 (in 1975, RG 1.87 was issued as Revision 1)

   
308/2025 
201/2023 
106/1975Periodic Review - February 2021 - Revise
 
Periodic Review – August 2019 – Withdraw
 
Periodic Review – August 2016 – Considerations
 
Periodic Review – November 2010 – No Action
1.88Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records
(Withdrawn -- See 56 FR 36175, 07/31/1991)
W07/1991 
210/1976 
1.89

Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants

204/2023 
106/1984Reviewed in 2018 – Revise

Periodic Review May 2014 - Revise
011/1974 
1.90

Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons

211/2012Reviewed in 2018 – Issues Identified for future consideration
108/1977 
011/1974 
1.91

Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants

311/2021 
204/2013Periodic Review – June 2020 - Revise
102/1978 
001/1975 
1.92

Combining Modal Responses and Spatial Components in Seismic Response Analysis

309/2012Reviewed in 2018 – Issues identified for future consideration
207/2006 
102/1976 
012/1974 
1.93

Availability of Electric Power Sources

103/2012Reviewed in 2017 – No issues identified
012/1974 
1.94

Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants
(Withdrawn -- See 75 FR 54921, 09/09/2010)

W09/2010 
104/1976 
004/1975 
1.95

Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release
(Withdrawn -- See 67 FR 939 01/08/2002)

W01/2002 
101/1977 
1.96Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants106/1976Periodic Review – August 2023 -Withdraw
 
Periodic Review - October 2013 – Considerations
005/1975 
1.97

Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants

505/2019 
406/2006 
305/1983 
212/1980 
108/1977 
012/1975 
1.98

Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor (for Comment)

003/1976Periodic Review in 2026 – Reviewed with issues identified for future consideration 

Periodic Review in 2016 – Issues identified for future consideration
1.99

Radiation Embrittlement of Reactor Vessel Materials

205/1988Periodic Review – November 2023 - Considerations

Technical Letter Report – July 2019 - Considerations

Periodic Review – January 2014 – No issues identified
104/1977 
007/1975 
1.100

Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants

405/2020 
309/2009 
206/1988 
108/1977 
003/1976 

Page Last Reviewed/Updated Friday, June 12, 2026

Page Last Reviewed/Updated Friday, June 12, 2026