Document: NUREG-0800
Document ID: 1c54f5f9-dd57-4543-a00d-1597061af2e0
Document Type: srp
Title: SEISMIC CLASSIFICATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1608/ML16084A812.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.2.1
CFR Part: 
CFR Title: 

Content:
RG 1.151 provides guidance for the proper seismic classification of safety-related instrumentation sensing lines used to actuate or monitor safety-related systems. 3.2.1-8 Revision 3 – July 2016 c. Compliance with the above requirements and guidance assures that the SSCs important to safety are properly classified as seismic Category I and will function during an SSE enabling accomplishment of the safety functions described above. 3. Compliance with GDC 60 requires, in part, that the nuclear power unit design include means to control suitably the release of radioactive materials in gaseous and liquid effluents. RG 1.143 provides acceptable methods and guidance relative to seismic design and classification for radioactive waste management SSCs. RG 1.143 also provides classification information and design criteria to assure that components and structures used in radioactive waste management systems are designed, constructed, installed and tested in a manner that protects the health and safety of the public and the plant operating personnel. Designing and constructing the radioactive waste management SSCs to meet the requirements of GDC 60 and the guidance on seismic design and classification contained in RG 1.143 provides assurance that SSCs containing radioactivity will be properly classified and radiation exposures as a result of seismic events will be as low as reasonably achievable. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. 1. RG 1.29, which identifies SSCs of light-water-cooled reactors on a functional basis, is the principal document used for identifying