Document: NUREG-0800
Document ID: 5dc31795-dfdc-4ed0-a4c2-e6a13e4997ab
Document Type: srp
Title: SEISMIC AND DYNAMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1608/ML16088A101.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.10
CFR Part: 
CFR Title: 

Content:
s should be performed for all supports of mechanical and electrical equipment to ensure their structural capability. ii. The analytical results should include the required input motions to the mounted equipment as obtained and characterized in the manner stated in Subsection I.1.A.iii above, and the combined stresses of the support structures should be in accordance with the criteria specified in SRP Section 3.9.3. iii. Supports, if qualified by test, should be tested with equipment installed or with a dummy simulating the equivalent equipment inertial mass effects and dynamic coupling to the support. If the equipment is installed in a nonoperational mode for the support test, the response in the test at the equipment mounting location should be monitored and characterized in the manner stated in Subsection II.1.A.iii above. In such a case, equipment should be tested separately for functionality, and the actual input motion to the equipment in this test should be higher in amplitude and frequency content than the monitored response from the support test. If the support structure or dummy is too large and/or too heavy for test shake table then only the equipment may be seismic tested based on simulated seismic input response at the equipment/support interface mounting location. The support structure may then be seismically analyzed. iv. The criteria of Subsections II.1.A.iii thru II.1.A.xiii above apply when tests are conducted on the equipment supports. C. Verification of Seismic and Dynamic Qualification. The seismic and dynamic qualification testing performed in accordance with IEEE Std. 344-2004, as endorsed by the NRC in RG 1.100, Revision 3, as part of an overall qualification program should be performed in the sequence indicated in Section 6 of IEEE Std. 323-1974 (endorsed with exceptions by the NRC in RG 1.89, “Environmental Qualification of Certain Electric Equipment Important to Safety for Nuclear Power Plants”). The IEEE Std. C37.98-2013 is, in