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 10 years, although in some cases a guide will reviewed before the normal 10 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.
| Guide Number |
Title | Rev. | Publish Date |
Reviewed |
|---|---|---|---|---|
| 1.141 | Containment Isolation Provisions for Fluid Systems | 1 | 07/2010 | 10/2015 |
| -- | 04/1978 | |||
| 1.142 | Safety-Related Concrete Structures for Nuclear Power Plants (Other than Reactor Vessels and Containments) | 2 | 11/2001 | 01/2015 |
| 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 | 03/2018 06/2015 |
| 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| 1.144 | Auditing of Quality Assurance Programs for Nuclear Power Plants (Withdrawn -- See 56 FR 36175, 07/31/1991) |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| 1.146 | Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants (Withdrawn -- See 56 FR 36175, 07/31/1991) |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 | 18 | 01/2018 | |
| 17 | 08/2014 | |||
| 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 | 07/2016 |
| 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 | 09/2016 |
| -- | 07/1983 | |||
| 1.152 | Criteria for Use of Computers in Safety Systems of Nuclear Power Plants | 3 | 07/2011 | 06/2016 |
| 2 | 01/2006 | |||
| 1 | 01/1996 | |||
| -- | 11/1985 | |||
| 1.153 | Criteria for Safety Systems (12/85) | 1 | 06/1996 | 04/2017 |
| -- | 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 | 09/2015 |
| 1.156 | Qualification of Connection Assemblies for Nuclear Power Plants | 1 | 07/2011 | 01/2017 |
| -- | 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 | 1 | 03/2018 | |
| -- | 02/1989 | 09/2016 08/2011 |
||
| 1.159 | Assuring the Availability of Funds for Decommissioning Nuclear Reactors | 2 | 10/2011 | 11/2016 |
| 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 |
