Document: NRC Regulatory Guide
Document ID: 1f8fd3ff-bc9e-4b84-b4d9-71d2a51882f7
Document Type: regulatory_guide
Title: Seismic Design Classification for Nuclear Power Plants + HISTORY - HISTORY DG-1315 , Proposed Revision 5, published 09/2015 DG-1156 , Proposed Revision 4, published 10/2006 (Rev. 5)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1506/ML15061A048.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.29
CFR Part: 
CFR Title: 

Content:
e found in Regulatory Guide 1.3, “Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Boiling-Water Reactors” (Ref. 12), Regulatory Guide 1.4, “Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for Pressurized-Water Reactors” (Ref. 13), and Regulatory Guide 1.183, “Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors” (Ref. 14). h. accident monitoring instrumentation. Regulatory Guide 1.97 contains specific criteria for instruments which need to be seismically qualified. Guidance is provided concerning seismic qualification and a safe shutdown earthquake. Accident monitoring DG-1315, Page 6 instrumentation Category 1 provides for full qualification, which includes seismic qualification. Instrumentation should continue to read within the required accuracy following a safe shutdown. 2. Those portions of SSCs of which continued function is not required but of which failure could reduce the functioning of any plant feature included in items 1.a through 1.h above to an unacceptable safety level, or could result in incapacitating injury to occupants of the control room should be designed and constructed so that the SSE would not cause such failure. Wherever practical, structures and equipment of which failure could possibly cause such injuries should be relocated or separated to the extent required to eliminate that possibility. 3. At the interface between seismic Category I and non-seismic Category I SSCs, the seismic Category I dynamic analysis requirements should be extended to either the first anchor point in the non-seismic system or a sufficient distance into the non-seismic Category I system so that the seismic Category I analysis remains valid. 4. The pertinent quality assurance requirements of Appendix B to 10 CFR Part 50 should be applied to all activities affecting the safety-related functions of