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 (last column on table) means that the NRC has reviewed these guides and has determined that they are acceptable for continued use. The NRC encourages comments from stakeholders on any Regulatory Guide at any time. Comments received in this manner will be reviewed upon receipt, but will be fully evaluated during the next periodic review of the affect guides. Currently, Regulatory Guides are reviewed on a 5 year basis. In certain cases, a Regulatory Guide will be looked at before the 5 year period has passed.
| 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| 1.144 | Auditing of Quality Assurance Programs for Nuclear Power Plants (Withdrawn -- See 56 FR 36175, 07/31/1991) |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 | |
| 1.145 | Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants | 1 | 02/1983 | |
| -- | 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| 1.146 | Qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants (Withdrawn -- See 56 FR 36175, 07/31/1991) |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 | |
| 1.147 | Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1 | 16 15 |
10/2010 10/2007 |
|
14 |
08/2005 |
|||
| 1.148 | Functional Specification for Active Valve Assemblies in Systems Important to Safety in Nuclear Power Plants (Withdrawn -- See 75 FR 2894, 01/19/2010) |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 | |
| 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 |
