Document: NUREG-0800
Document ID: 7d53889c-d236-4e84-9579-a2beb4716167
Document Type: srp
Title: SEISMIC CLASSIFICATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070296.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.2.1
CFR Part: 
CFR Title: 

Content:
ll be designed, constructed and operated under a Quality Assurance Program, in compliance with the requirements of 10 CFR Part 50, Appendix B.65 2. The applicant having met the requirements of General Design Criterion 2, and 10 CFR Part 100, Appendix A, by having properly classified their structures, systems and components (SSCs) important to safety as seismic Category I items 66 in accordance with the positions of Regulatory Guide 1.29, "Seismic Design Classification," and Regulatory Guide 1.151, "Instrument Sensing Lines." and 67 by our conclusion that The identified SSCs are thethose plant features 68 69 necessary to assure (1) the integrity of the reactor coolant pressure boundary, (2) the capability to shutdown the reactor and maintain it in a safe shutdown condition, and (3) the capability to prevent and mitigate the consequences of accidents which could result in potential offsite exposures comparable to the guideline exposures of 10 CFR Part 100. 3.2.1-9 DRAFT Rev. 2 - April 1996 3. Those SSCs not identified as seismic Category I, but whose failure could reduce the functioning of any seismic Category I feature to an unacceptable safety level or result in incapacitating injury to control room personnel, are identified for analysis to assure they will not fail during a SSE.70 4. Radioactive waste system SSCs requiring seismic design considerations have been identified consistent with the positions of Regulatory Guide 1.143.71 5. (For BWRs, also include the following finding) The applicant has properly classified the main steam and associated systems in accordance with the guidance contained in Appendices A and B of SRP Section 3.2.2.72 For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff's evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and