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 (NUREG-1482, Revision 3)

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Publication Information

Manuscript Completed: July 2020
Date Published: July 2020

Prepared by:
Gurjendra S. Bedi

Office of Nuclear Reactor Regulation

Availability Notice


The staff of the U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 3 to the 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. 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 the OM Code at operating commercial nuclear power plants, and the development of IST programs for new reactors1.

This NUREG report replaces Revision 0, Revision 1 and Revision 2 to NUREG-1482 and is applicable, unless stated otherwise, to editions and addenda (up to and including the 2017 Edition) to the OM Code, that are incorporated by reference in Title 10 of the Code of Federal Regulations (10 CFR) 50.55a. 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 2 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 3, are from the 2017 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 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 Plants."

1 New Reactor (referred to as a post-2000 reactor in the ASME OM Code) is defined in NUREG-1482 as a nuclear plant 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.

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