Report a Safety Concern
Search

The U.S. Nuclear Regulatory Commission is in the process of rescinding or revising guidance and policies posted on this webpage in accordance with Executive Order 14151 Ending Radical and Wasteful Government DEI Programs and Preferencing, and Executive Order 14168 Defending Women From Gender Ideology Extremism and Restoring Biological Truth to the Federal Government. In the interim, any previously issued diversity, equity, inclusion, or gender-related guidance on this webpage should be considered rescinded that is inconsistent with these Executive Orders.

Home NRC Library Document Collections NUREG-Series Publications Publications Prepared by NRC Staff NUREG-1482

Guidelines for Inservice Testing at Nuclear Power Plants: Inservice Testing of Pumps and Valves and Inservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants — Draft Report for Comment (NUREG-1482, Revision 4)

This NUREG-series publication was issued for public comment. The comment period is now closed.

On this page:

Download complete document

Publication Information

Manuscript Completed: December 2024
Date Published: February 2025

Prepared by:
Nicholas Hansing

Office of Nuclear Reactor Regulation

Availability Notice

Abstract

The staff of the U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 4 to NUREG-1482, "Guidelines for Inservice Testing at Nuclear Power Plants," to assist the nuclear industry in establishing a basic understanding of the regulatory basis for pump and valve inservice testing (IST) programs and dynamic restraint (snubbers) examination and testing programs at nuclear power plants. This NUREG also provides information regarding the NRC's involvement in the development of the American Society of Mechanical Engineers (ASME) "Operation and Maintenance of Nuclear Power Plants," Division 1, "OM Code: Section IST" (OM Code). In this NUREG, the NRC staff discusses OM Code inquiries, the inservice examination and testing of snubbers, pump and valve IST, the use of ASME Code Cases, conditions on the use of the OM Code, guidance for OM Code noncompliance, requests for alternatives to and relief from the OM Code at operating commercial nuclear power plants, and the development of IST programs for new reactors.*

This NUREG report replaces Revision 0, Revision 1, Revision 2, and Revision 3 to NUREG-1482 and is applicable, unless stated otherwise, to editions and addenda (up to and including the 2020 Edition) to the OM Code that are incorporated by reference in Title 10 of the Code of Federal Regulations (10 CFR) 50.55a, "Codes and standards." In addition, the NRC staff discusses other IST program topics such as the NRC process for the review of the OM Code, conditions on the use of the OM Code, interpretations of the OM Code, and development of IST programs for new reactors. In this NUREG, the NRC staff provides guidance included in Revision 3 to NUREG-1482 that has been updated to reflect IST lessons learned and operating experience since the NUREG was previously issued.

All subsections and paragraphs used in NUREG-1482, Revision 4, are from the 2020 Edition of the OM Code as incorporated by reference in 10 CFR 50.55a, unless otherwise noted. Appendix A (page 191 of the document) contains guidance related to inservice examination and testing of snubbers. Appendix B (page 241 of the document) contains guidance related to the treatment of pumps, valves, and dynamic restraints during implementation of 10 CFR 50.69, "Risk-informed categorization and treatment of structures, systems and components for nuclear power reactors." Appendix C contains guidance related to the "code of record" interval.

This revision to NUREG-1482 focuses on the 2020 Edition of the OM Code and does not attempt to address every provision in the editions and addenda of the OM Code prior to the 2020 Edition. In some cases where an IST provision does not appear in the 2020 Edition of the OM Code, this revision to NUREG-1482 might not discuss that provision. Prior revisions to NUREG-1482 might discuss IST provisions that have been removed from the OM Code as new editions and addenda have been prepared by ASME. For example, Revision 3 of NUREG-1482 is based on the 2017 Edition of the OM Code and may be referenced for specific code language from that edition.

* “New reactor” (referred to as a post-2000 plant in the OM Code) is defined in NUREG-1482 as a nuclear power reactor that was issued (or will be issued) its construction permit or combined license for construction and operation by the applicable regulatory authority on or following January 1, 2000.

Paperwork Reduction Act

This NUREG contains voluntary guidance for implementing the mandatory information collections covered by 10 CFR Parts 50.55a, and 10 CFR Part 50 and 52 that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et. seq.). These information collections were approved by the Office of Management and Budget (1 OMB), under control numbers 3150-0264, 3150-0011, and 3150-0151, respectively. Send comments regarding this information collection to the FOIA, Library, and Information Collections Branch (T6-A10M), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the OMB Office of Information and Regulatory Affairs (3150-0264, 3150-0011, and 3150-0151), attention Desk Officer for the Nuclear Regulatory Commission, 725 17th Street NW, Washington, DC 20503.

Public Protection Notification

The NRC may not conduct or sponsor, and a person is not required to respond to, a collection of information unless the document requesting or requiring the collection displays a currently valid OMB control number.

Page Last Reviewed/Updated Wednesday, April 16, 2025