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Resolution of Generic Safety Issues: Issue 21: Vibration Qualification of Equipment (Rev. 2) ( NUREG-0933, Main Report with Supplements 1–35 )


This issue originated from NUREG-05724 where the ACRS identified vibration-induced equipment failures resulting from various loading conditions; it was later included in the initial list23 of new issues that were identified for prioritization. Since the identification of this issue, the staff has addressed vibration-induced equipment failures resulting from a number of sources, e.g., flow-induced vibration (Issue 7), dynamic water hammer loads (Issue A-1), safety relief valve loads (Issue A-8), asymmetric loads (Issue A-2), and seismic loads. These issues are discussed in Sections 2 and 3 of this report.

The seismic loads and their resulting vibration effects on equipment fragility and operability were addressed in the following issues: A-40, "Seismic Design Criteria"; A-41, "Long-Term Seismic Program"; A-46, "Seismic Qualification of Equipment in Operating Plants"; B-24, "Seismic Qualification of Electrical and Mechanical Components"; and B-52, "Fuel Assembly Seismic and LOCA Responses." Other issues that address potential vibration-induced problems include C-12, "Primary System Vibration Assessment," and B-73, "Monitoring for Excessive Vibration Inside the Reactor Pressure Vessel."

It is evident from the above issues that vibration-related problems can arise from many sources and no single, simple, overall solution is appropriate for the broad spectrum of problems. However, since the ACRS identified this issue, the staff revised the vibration qualification guidance in SRP11 Sections 3.9.2 and 3.10 (see Issue B-24). In addition, the above issues addressed specific vibration problems that were handled by the staff on a case-by-case basis.


Based on the actions identified above, the original ACRS concerns were addressed by the SRP11 revisions and the related issues that were resolved on a case-by-case basis. Thus, this issue was DROPPED as a separate issue.


0004.NUREG-0572, "Review of Licensee Event Reports (1976–1978)," U.S. Nuclear Regulatory Commission, September 1979.
0011. NUREG-0800, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants," U.S. Nuclear Regulatory Commission, (1st Ed.) November 1975, (2nd Ed.) March 1980, (3rd Ed.) July 1981.
0023.Memorandum for Distribution from W. Minners, "Generic Issues Screening Activity," September 30, 1981. [8110190695]