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BS ISO 4917-6:2024 Design of nuclear power plants against seismic events - Post-seismic measures, 2024
- undefined
- Foreword
- Introduction
- 1 Scope
- 2 Normative references
- 3 Terms and definitions
- 4 Procedure [Go to Page]
- 4.1 General requirements
- 4.2 Verification of the earthquake
- 4.3 Classification of the earthquake
- 4.4 Initial measures [Go to Page]
- 4.4.1 Plant check-up from the control room and plant walk-down inspection (Figure 2, chart item 3)
- 4.4.2 Deviations caused by the earthquake (Figure 2, chart item 4)
- 4.4.3 Specified normal operation condition in accordance with the operating manual (Figure 2, chart item 5)
- 4.5 In-depth measures [Go to Page]
- 4.5.1 General
- 4.5.2 Special/Seismic inspections and analyses (Figure 2, chart item 6)
- 4.5.3 Specified normal operation condition and permissible loads (Figure 2, chart item 7)
- 4.5.4 Shutdown inspection (Figure 2, chart item 9)
- 4.6 Resulting measures [Go to Page]
- 4.6.1 Continued operation (Figure 2, chart item 8)
- 4.6.2 Shutting down the plant (Figure 2, chart item 10)
- 4.6.3 Additional procedures (Figure 2, chart item 11)
- Annex A (informative) Derivation of factor, f
- Annex B (informative) Directives for plant walk-down inspections
- Annex C (informative) Special/Seismic inspections
- Bibliography [Go to Page]