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Power Reactors (Division 1): Regulatory Guides 1.141 - 1.160

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
1.141 Containment Isolation Provisions for Fluid Systems 1 07/2010  
-- 04/1978  
1.142 Safety-Related Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments) 2 11/2001  
1 10/1981  
-- 04/1978  
1.143 Design Guidance for Radioactive Waste Management Systems, Structures, and Components Installed in Light-Water-Cooled Nuclear Power Plants 2 11/2001  
1 10/1979  
-- 07/1978  
1.144 Auditing of Quality Assurance Programs for Nuclear Power Plants
(Withdrawn -- See 56 FR 36175, 07/31/1991)
W 07/1991  
1 09/1980  
1.145 Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants 1 02/1983 04/2014
-- 08/1979  
1.146 Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants
(Withdrawn -- See 56 FR 36175, 07/31/1991)
W 07/1991  
08/1980  
1.147 Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1 17 10/2014  
16 10/2010  
15 10/2007  
    14
08/2005  
    13-R 01/2004  
    13 06/2003  
    12 05/1999  
    11 10/1994  
    10 07/1993  
    9 04/1992  
    8 11/1990  
    7 07/1989  
    6 05/1988  
    5 08/1986  
    4 09/1985  
    3 07/1984  
    2 06/1983  
    1 02/1982  
    -- 02/1981  
1.148 Functional Specification for Active Valve Assemblies in Systems Important to Safety in Nuclear Power Plants
(Withdrawn -- See 75 FR 2894, 01/19/2010)
W 01/2010  
-- 03/1981  
1.149 Nuclear Power Plant Simulation Facilities for Use in Operator Training and License Examinations 4 04/2011  
3 10/2001  
2 04/1996  
1 04/1987  
-- 04/1981  
1.150 Ultrasonic Testing of Reactor Vessel Welds During Preservice and Inservice Examinations
(Withdrawn-- See 73 FR 7766, 02/11/2008
W 02/2008  
-- 02/1983  
1.151 Instrument Sensing Lines 1 07/2010  
-- 07/1983  
1.152 Criteria for Use of Computers in Safety Systems of Nuclear Power Plants 3 07/2011  
2 01/2006  
1 01/1996  
-- 11/1985  
1.153 Criteria for Safety Systems (12/85) 1 06/1996  
-- 12/1985  
1.154 Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors
(Withdrawn -- See 76 FR 2726, 01/14/2011)
W 01/2011  
-- 01/1987  
1.155 Station Blackout -- 08/1988  
1.156 Qualification of Connection Assemblies for Nuclear Power Plants 1 07/2011  
-- 11/1987  
1.157 Best-Estimate Calculations of Emergency Core Cooling System Performance -- 05/1989 04/2013
1.158 Qualification of Safety-Related Lead Storage Batteries for Nuclear Power Plants -- 02/1989 08/2011
1.159 Assuring the Availability of Funds for Decommissioning Nuclear Reactors 2 10/2011  
1 10/2003  
-- 08/1990  
1.160 Monitoring the Effectiveness of Maintenance at Nuclear Power Plants 3 05/2012  
2 03/1997  
1 01/1995  
-- 06/1993  

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Page Last Reviewed/Updated Wednesday, October 22, 2014