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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 Division 1.

See NRC Regulatory Guides for more general information.

Reviewed dates (the last column in the table) are when the staff completed a periodic review of the associated guide. Regulatory Guides are reviewed about every 5 years, although in some cases a guide will reviewed before the normal 5 year period. 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.

The NRC encourages suggestions from stakeholders regarding any Regulatory Guide or development of new guides at any time. Suggestions received in this manner will be reviewed upon receipt, but will typically be fully evaluated during the next periodic review of the affect guides.

Guide
Number
Title Rev. Publish
Date
Reviewed
1.81 Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants 1 01/1975 02/2014
-- 06/1974  
1.82 Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident 4 03/2012  
3 11/2003 04/2012
2 05/1996  
1 11/1985  
-- 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(Withdrawn -- See 74 FR 58324, 11/12/2009)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  
-- 07/1974  
1.84 Design, Fabrication, and Materials Code Case Acceptability, ASME Section III 36 10/2014  
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  
-- 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(Withdrawn See -- 69 FR 34202 06/18/2004)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 -- 06/1974 12/2011
1.87 Guidance for Construction of Class 1 Components in Elevated-Temperature Reactors -- 06/1975 11/2010
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 1 06/1984 05/2014
-- 11/1974  
1.90 Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons 2 11/2012  
1 08/1977  
-- 11/1974  
1.91 Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants 2 04/2013  
1 02/1978  
-- 01/1975  
1.92 Combining Modal Responses and Spatial Components in Seismic Response Analysis 3 09/2012  
2 07/2006  
1 02/1976  
-- 12/1974  
1.93 Availability of Electric Power Sources 1 03/2012  
-- 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  
-- 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  
-- 05/1975  
1.97 Criteria for Accident Monitoring Instrumentation for Nuclear Power Plants 4 06/2006 06/2013
3 05/1983  
2 12/1980  
1 08/1977  
-- 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) -- 03/1976 10/2010
1.99 Radiation Embrittlement of Reactor Vessel Materials 2 05/1988 01/2014
1 04/1977  
-- 07/1975  
1.100 Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants 3 09/2009  
2 06/1988 09/2009
1 08/1977  
-- 03/1976  

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Page Last Reviewed/Updated Wednesday, October 22, 2014