Document: NUREG-0800
Document ID: bff27319-5835-4b67-a4f5-815264004d90
Document Type: srp
Title: SPENT FUEL POOL COOLING AND CLEANUP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070505.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.1.3
CFR Part: 
CFR Title: 

Content:
and filtration 58 system meet this criterion, and the ventilation and filtration system meets the guidelines of Regulatory Guide 1.52. The cooling and makeup system should also be designed to Quality Group C 59 60 requirements in accordance with Regulatory Guide 1.26. However, when the cooling system is not designated Category I it need not meet the requirements of ASME Section XI for inservice inspection of nuclear plant components. b. General Design Criterion 4 (GDC 4), with respect to structures housing the 61 systems and the system being capable of withstanding the effects of external missiles. Acceptance is based on meeting position C.2 of Regulatory Guide 1.13. This criterion does not apply to the cleanup system and need not apply to the 62 cooling water system if the makeup system, and its source, and the building, and its ventilation and filtration system are tornado protected, and the ventilation and filtration system meets the guidelines of Regulatory Guide 1.52.63 DRAFT Rev. 2 - April 1996 9.1.3-6 c. General Design Criterion 5 (GDC 5), as related to shared systems and 64 components important to safety being capable of performing required safety functions. d. General Design Criterion 44 (GDC 44), to includeas related to : 65 66 (1) The capability to transfer heat loads from safety-related structures, systems, and components to a heat sink under both normal operating and accident conditions. (2) Suitable redundancy of components so that safety functions can be performed assuming a single active failure of a component coincident with the loss of all offsite power. (3) The capability to isolate components, systems, or piping, if required, so that the system safety function will not be compromised. (4) In meeting this criterion, acceptance is based on the recommendations of 67 Branch Technical Position ASB 9-2 SPLB 9-2, "Residual Decay Energy for Light-Water Reactors for Long-Term Cooling" (located in SRP Section 9.2.5) for calculating the heat loads and the