Document: NRC Regulatory Guide
Document ID: 37f53017-d71c-4f3c-a2a4-ab67a8270066
Document Type: regulatory_guide
Title: Pre-Earthquake Planning, Shutdown, and Restart of a Nuclear Power Plant Following an Earthquake (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1826/ML18268A185.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.166
CFR Part: 
CFR Title: 

Content:
ich components were selected and how the sample population was narrowed should be documented and available for NRC inspection. Any issues that are identified should be evaluated in accordance with the guidance provided in Section 9 of ANSI/ANS-2.23-2016 to ascertain operability consistent with NRC Inspection Manual Chapter (IMC) 0326. C. 2 Clarification of Post-shutdown Inspection and Test Documentation Requirements in Section ANSI/ANS-2.23-2016, Section 8.8 The documentation described in Section 8.8 of ANSI/ANS-2.23-2016 should be available for NRC inspection prior to restart. The documentation should include the condition report methodology, assumptions, assessments, technical specification (TS) surveillance requirement number for each surveillance test, and other inspections that demonstrated that the operability of all safety-related SSCs was not affected. In addition, the documentation should demonstrate that any nonsafety-related SSC impacts are corrected or that the risk is properly managed in accordance with 10 CFR 50.65, “Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants.” Specifically, if DG-1337, Page 7 the plant is restarted with nonsafety-related equipment impacts left uncorrected or unevaluated, the increase in risk must be monitored and accounted for in daily risk assessments as required by 10 CFR 50.65. C.3 Clarification of Seismic Evaluation and Verification Plans in ANSI/ANS-2.23-2016, Section 9.5 Section 9.5 of ANSI/ANS-2.23-2016 provides guidance on developing a seismic evaluation and verification plan. Section 9.5 states that the plan should require the new and replacement safety-related SSCs to be qualified to both the licensing-basis design spectra and the observed spectra unless the licensee can demonstrate using appropriate risk-informed or performance-based approaches that the SSCs involved do not pose a significant seismic risk. All new or replacement equipment must meet current or amended site