Skip to main content

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

Title

Revision Number

Issue
Date

Additional Information

1.81

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

1

01/1975

Reviewed in 2019 – No issues identified

0

06/1974

 

1.82

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

5

08/2022

 

4

03/2012

01/2015 – PR – Revise

3

11/2003

 

2

05/1996

 

1

11/1985

 

0

06/1974

 

1.83

Inservice Inspection of Pressurized Water Reactor Steam Generator Tubes
(Withdrawn -- See 74 FR 58324, 11/12/2009)

W

11/2009

 

1

07/1975

 

0

07/1974

 

1.84

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

40

03/2024

07/2024: Final Rule Federal Register Notice

39

12/2021

03/2022: Final Rule Federal Register Notice

38

10/2019

03/2020: Final Rule Federal Register Notice

37

03/2017

01/2018: Final Rule Federal Register Notice

36

08/2014

 

35

10/2010

 

34

10/2007

 

33

08/2005

 

32

06/2003

 

31

05/1999

 

30

10/1994

 

29

07/1993

 

28

04/1992

 

27

11/1990

 

26

07/1989

 

25

05/1998

 

24

06/1986

 

23

09/1985

 

22

07/1984

 

21

09/1983

 

20

11/1982

 

19

04/1982

 

18

08/1981

 

17

12/1980

 

16

05/1980

 

15

05/1979

 

14

11/1978

 

13

07/1978

 

12

03/1978

 

11

11/1977

 

10

08/1977

 

9

03/1977

 

8

11/1976

 

7

08/1976

 

6

05/1976

 

5

03/1976

 

4

11/1975

 

3

09/1975

 

2

06/1975

 

1

04/1975

 

0

06/1974

 

1.85

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(Withdrawn See -- 69 FR 34202 06/18/2004)

W

06/2004

 

31

05/1999

 

30

10/1994

 

27

11/1990

 

26

07/1989

 

23

09/1985

 

22

07/1984

 

21

09/1983

 

17

12/1980

 

16

05/1980

 

15

05/1979

 

14

11/1978

 

13

07/1978

 

12

03/1978

 

11

11/1977

 

10

08/1977

 

9

03/1977

 

8

11/1976

 

7

08/1976

 

6

05/1976

 

5

02/1976

 

4

11/1975

 

3

09/1975

 

2

06/1975

 

1

04/1975

 

0

06/1974

 

1.86

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(Withdrawn -- See 81 FR 53507, 08/12/2016)

W

08/2016

 

0

06/1974

 

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)

3

08/2025

 

2

01/2023

 

1

06/1975

Periodic Review - February 2021 - Revise
 
Periodic Review – August 2019 – Withdraw
 
Periodic Review – August 2016 – Considerations
 
Periodic Review – November 2010 – No Action

1.88

Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records
(Withdrawn -- See 56 FR 36175, 07/31/1991)

W

07/1991

 

2

10/1976

 

1.89

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

2

04/2023

 

1

06/1984

Reviewed in 2018 – Revise

Periodic Review May 2014 - Revise

0

11/1974

 

1.90

Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons

2

11/2012

Reviewed in 2018 – Issues Identified for future consideration

1

08/1977

 

0

11/1974

 

1.91

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

3

11/2021

 

2

04/2013

Periodic Review – June 2020 - Revise

1

02/1978

 

0

01/1975

 

1.92

Combining Modal Responses and Spatial Components in Seismic Response Analysis

3

09/2012

Reviewed in 2018 – Issues identified for future consideration

2

07/2006

 

1

02/1976

 

0

12/1974

 

1.93

Availability of Electric Power Sources

1

03/2012

Reviewed in 2017 – No issues identified

0

12/1974

 

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)

W

09/2010

 

1

04/1976

 

0

04/1975

 

1.95

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

W

01/2002

 

1

01/1977

 

1.96

Design of Main Steam Isolation Valve Leakage Control Systems for Boiling Water Reactor Nuclear Power Plants

1

06/1976

Periodic Review – August 2023 -Withdraw
 
Periodic Review - October 2013 – Considerations

0

05/1975

 

1.97

Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants

5

05/2019

 

4

06/2006

 

3

05/1983

 

2

12/1980

 

1

08/1977

 

0

12/1975

 

1.98

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

0

03/1976

Reviewed in 2016 – Issues identified for future consideration

1.99

Radiation Embrittlement of Reactor Vessel Materials

2

05/1988

Periodic Review – November 2023 - Considerations

Technical Letter Report – July 2019 - Considerations

Periodic Review – January 2014 – No issues identified

1

04/1977

 

0

07/1975

 

1.100

Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants

4

05/2020

 

3

09/2009

 

2

06/1988

 

1

08/1977

 

0

03/1976

 

Page Last Reviewed/Updated Friday, January 16, 2026

Page Last Reviewed/Updated Friday, January 16, 2026