Document: NUREG-0800
Document ID: 2ff4b7bf-0033-46ea-abe0-313b6bff2ac6
Document Type: srp
Title: SEISMIC CLASSIFICATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190002.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.2.1
CFR Part: 
CFR Title: 

Content:
ewed to assure that these plant features are within the scope of an applicant's QA Program. This QA Program should be in compliance with the pertinent QA requirements of 10 CFR Part 50, Appendix B. In accordance with RG 1.29, the pertinent QA requirements of Appendix B to 10 CFR Part 50 should be applied to all activities affecting the safety-related functions of Seismic Category I SSCs. If there are items designated Seismic Category I that are not identified as within the scope of the 10 CFR Part 50, Appendix B, QA Program, then this information is transmitted to the staff for resolution of the issue. The seismic classification review of SSCs important to safety and the review verifying that these plant features are constructed in accordance with a 10 CFR Part 50, Appendix B, QA Program is normally performed concurrently with the quality group classification review of SRP Section 3.2.2. 3.2.1-8 Revision 2 - March 2007 Other SSCs that may be required for operation of the facility (excluding electrical features) need not be designed to Seismic Category I requirements. Those SSCs not required to be designed to seismic Category I requirements include those portions of Seismic Category I systems such as vent lines, drain lines, fill lines and test lines on the downstream side of isolation valves and those portions of the system not required to perform a safety function. 4. Classification guidelines for selected BWR main steam system SSCs are addressed in SRP Section 3.2.2 Appendix A. For General Electric BWR/6 main steam lines and main feedwater lines, an acceptable alternate seismic classification to that currently specified in Position C.1.e of RG 1.29 is provided in Figure B-1 attached to Appendix B of SRP Section 3.2.2. For BWRs that do not include a main steam isolation valve leakage control system, and for which main steam line fission product hold-up and retention is credited in the analysis of design basis accident radiological consequences, an acceptable