Document: NUREG-0800
Document ID: 3571c6d8-6b1b-4c29-884c-33ab5be58d7f
Document Type: srp
Title: SEISMIC INSTRUMENTATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0704/ML070460349.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.7.4
CFR Part: 
CFR Title: 

Content:
nt of the baseline inspections, that are to be taken immediately after an earthquake, as described in RG 1.166. With regard to the evaluation of ground motion records, the applicant’s program should describe data identification (i.e., record collection log), data collection, and record evaluation procedures. Shutdown of the nuclear power plant is required if the vibratory ground motion experienced exceeds that of the OBE. A criterion for determining exceedance of the OBE is provided in the Electric Power Research Institute (EPRI) document EPRI NP-5930, “A Criterion for Determining Exceedance of the Operating Basis Earthquake.” This criterion is based on a threshold response spectrum ordinate check and a cumulative absolute velocity (CAV) check. The ground motion evaluation should consist of a check on the response spectrum and CAV and a check on the operability of the instrumentation as described in RG 1.166. This evaluation should take place within 4 hours of the earthquake. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 10 CFR Part 50, Appendix S, requires that suitable instrumentation be provided to promptly evaluate the seismic response of nuclear power plant features important to safety after an earthquake. Appendix S also requires shutdown of the nuclear power plant if vibratory ground motion exceeding that of the OBE occurs. The seismic instrumentation program with installation of solid-state digital time-history accelerographs at appropriate locations will provide time history data on the seismic response of the free-field, containment structure, and other Seismic Category I structures, as well as maintaining occupational radiation exposures ALARA for the location as required by 10 CFR Part 20. 3.7.4-5 Revision 2 - March 2007 III. REVIEW PROCEDURES The reviewer will select material from the procedures described below,