Document: NUREG-0800
Document ID: 02fef38f-79ed-4d55-825f-81551bcfdcdc
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550016.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
he safety analysis with regard to automatic actuation, remote sensing, indication, control, and interlocks with auxiliary or shared systems under SRP Sections 7.2 and 7.3. On request, the organization responsible for instrumentation and controls evaluates the failure modes analysis of the ECCS to verify that an adequate analysis of possible failure modes of ECCS instrumentation and controls equipment and the effect of the failure modes of that equipment on the ECCS performance has been provided. 6. The organization responsible for the review of electrical engineering as part of its review of SRP sections 8.3.1 and 8.3.2 evaluates the emergency onsite power functional capabilities. Also, on request, the electrical engineering reviewer will verify that the control systems power sources needed to function to mitigate the event are available as required by the applicant's description of the event. On request, the organization responsible for the review of electrical engineering evaluates the failure modes analysis of the ECCS to verify that an adequate analysis of possible failure modes of ECCS equipment and the effect of the failure modes on the ECCS performance has been provided. 15.6.5-5 Revision 3 - March 2007 7. Evaluation of auxiliary systems (e.g., auxiliary feedwater, service water system, component cooling system, ultimate heat sink, condensate storage facility) to confirm that these systems can supply all the functions required to support the ECCS in performing its function during and following a loss-of-coolant accident is reviewed in the applicable SRP Sections in Chapter 9 and 10. Integrity of the reactor coolant pump seals is performed under SRP Section 9.2.2. 8. Effects of the combined blowdown and seismic loads on core support structures and on control rod guide structures under SRP Sections 3.6.2, 3.9.2, 3.9.3, 3.9.4, and 3.9.5. On request from the lead reviewer for this section, the reviewer of the interfacing section verifies that the core remains in