Power Reactors (Division 1): Regulatory Guides 1.161 - 1.180
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.
|1.161||Evaluation of Reactor Pressure Vessels with Charpy Upper-Shelf Energy Less Than 50 Ft-Lb||--||06/1995||03/2014|
|1.162||Format and Content of Report for Thermal Annealing of Reactor Pressure Vessels||--||02/1996||12/2014
|1.163||Performance-Based Containment Leak-Test Program||--||09/1995||12/2014|
|1.164||(Not yet issued)|
|1.165||Identification and Characterization of Seismic Sources and Determination of Safe Shutdown Earthquake Ground Motion
(Withdrawn -- See 75 FR 22868, 04/30/2010)
|1.166||Pre-Earthquake Planning and Immediate Nuclear Power Plant Operator Postearthquake Actions||--||03/1997||04/2015|
|1.167||Restart of a Nuclear Power Plant Shut Down by a Seismic Event||--||03/1997||01/2015|
|1.168||Verification, Validation, Reviews, and Audits for Digital Computer Software Used in Safety Systems of Nuclear Power Plants||2||07/2013|
|1.169||Configuration Management Plans for Digital Computer Software Used in Safety Systems of Nuclear Power Plants||1||07/2013|
|1.170||Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants||1||07/2013|
|1.171||Software Unit Testing for Digital Computer Software Used in Safety Systems of Nuclear Power Plants||1||07/2013|
|1.172||Software Requirement Specifications for Digital Computer Software and Complex Electronics Used in Safety Systems of Nuclear Power Plants||1||07/2013|
|1.173||Developing Software Life Cycle Processes for Digital Computer Software Used in Safety Systems of Nuclear Power Plants||1||07/2013|
|1.174||An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis||2||05/2011|
|1.175||An Approach for Plant-Specific, Risk-Informed Decisionmaking: Inservice Testing||--||08/1998||03/2010|
|1.176||An Approach for Plant-Specific, Risk-Informed Decisionmaking: Graded Quality Assurance
(Withdrawn-- See 73 FR 7766, 02/11/2008)
|1.177||An Approach for Plant-Specific, Risk-Informed Decisionmaking: Technical Specifications||1||05/2011|
|1.178||An Approach for Plant-Specific Risk-Informed Decisionmaking for Inservice Inspection of Piping||1||09/2003||03/2010|
|1.179||Standard Format and Content of License Termination Plans for Nuclear Power Reactors||1||06/2011|
|1.180||Guidelines for Evaluating Electromagnetic and Radio-Frequency Interference in Safety-Related Instrumentation and Control Systems||1||10/2003||06/2011|