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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.

Guide
Number
Title Rev. Publish
Date
Reviewed
1.81 Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants 1 01/1975  
-- 06/1974
1.82 Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident 4 03/2012  
3 11/2003
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(Withdrawn -- See 74 FR 58324, 11/12/2009)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
-- 06/1974
1.84 Design, Fabrication, and Materials Code Case Acceptability, ASME Section III 35
34
10/2010
10/2007
 

33
32
31
30
29
28
27
26
25
24
23
22
21
20
19
18
17
16
15
14
13
12
11
10
9
8
7
6
5
4
3
2
1
--

08/2005
06/2003
05/1999
10/1994
07/1993
04/1992
11/1990
07/1989
05/1998
06/1986
09/1985
07/1984
09/1983
11/1982
04/1982
08/1981
12/1980
05/1980
05/1979
11/1978
07/1978
03/1978
11/1977
08/1977
03/1977

08/1976
05/1976
03/1976
11/1975
09/1975
06/1975
04/1975
06/1974

1.85 Materials code case Acceptability - - ASME Section III, Division 1
(Withdrawn 06/01/2003)
W 06/2003  
31 05/1999
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 Record
(Withdrawn -- See 56 FR 36175, 07/31/1991)
W 07/1991  
1.89 Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants 1 06/1984  
-- 11/1974
1.90 Inservice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons 1 08/1977  
-- 11/1974
1.91 Evaluations of Explosions Postulated To Occur on Transportation Routes Near Nuclear Power Plants 1 02/1978  
-- 01/1975
1.92 Combining Modal Responses and Spatial Components in Seismic Response Analysis 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 01/01/2002)
W 01/2002  
0 01/1997
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  
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  
1 04/1977
-- 07/1975
1.100 Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants 3 09/2009  
2 06/1988
1 08/1977
-- 03/1976

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Page Last Reviewed/Updated Tuesday, August 28, 2012