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 — Final Report (NUREG-1482, Revision 4)

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Publication Information

Manuscript Completed: September 2025
Date Published: September 2025

Prepared by:
Nicholas Hansing

Office of Nuclear Reactor Regulation

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Abstract

The staff of the U.S. Nuclear Regulatory Commission (NRC, the Commission) 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 about 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). This NUREG 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 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 2022 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. This NUREG 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 referred to in this revision of NUREG-1482 are from the 2022 Edition of the OM Code as incorporated by reference in 10 CFR 50.55a, unless otherwise noted. Appendix A contains guidance related to inservice examination and testing of snubbers. Appendix B responds to public comments related to the Commission direction in the NRC Federal Register notice for 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 2022 Edition of the OM Code and does not attempt to address every provision in the editions and addenda of the OM Code before the 2022 Edition. In some cases where an IST provision does not appear in the 2022 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.