Seismically rugged aka seismically robust is a general term used to describe whether a SSC is designed to withstand a Safe Shutdown Earthquake (SSE). The term is often used in regard to Fukushima seismic responses.
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| ML25042A010 | 24 January 2025 | | 1-08-2025 Part 53 Proposed Rule Public Meeting Summary | | RBG-48323, License Amendment Request to Revise the Licensing Basis and Minimum Basin Water Level for the Ultimate Heat Sink | 30 December 2024 | River Bend | License Amendment Request to Revise the Licensing Basis and Minimum Basin Water Level for the Ultimate Heat Sink | | ML24304A864 | 12 November 2024 | | DG-1425 (RG 1.183 Rev 2) Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors ACRS Version | | IR 05000261/2024011 | 3 June 2024 | Robinson | Focused Engineering Inspection- Commercial Grade Dedication Report 05000261/2024011 | | RBG-48271, Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk | 12 January 2024 | River Bend | Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk | | ML23291A415 | 12 October 2023 | Susquehanna | 1 to Updated Final Safety Analysis Report, Chapter 6, Section 6.7, Main Steam Isolation Valve Leakage Isolated Condenser Treatment Method | | ML23082A305 | 10 October 2023 | | Regulatory Guide (RG) 1.183, Revision 1, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors | | ML23082A309 | 10 October 2023 | | DG-1389 (RG 1.183 Rev 1) Public Comment Resolution Table | | ML23194A013 | 31 August 2023 | | Level 3 PRA Project, Volume 4d Reactor, At-Power, Level 2 PRA for Internal Fires, Seismic Events, and High Winds; Draft Report for Release | | ML23243B012 | 31 August 2023 | | Rev. 1, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactor (Pre-decisional) ACRS Version |
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