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:
endations 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 assumptions set 68 forth in item 1.h of subsection III of this SRP section. The temperature limitations of the pool water identified in item 1.d of subsection III of this SRP section is also used as a basis for meeting this criterion. e. General Design Criterion 45 (GDC 45), as related to the design provisions to 69 permit periodic inspection of safety-related components and equipment. f. General Design Criterion 46 (GDC 46), as related to the design provisions to 70 permit operational functional testing of safety-related systems or components to assureensure structural integrity and system leak tightness, operability, and 71 adequate performance of active system components, and the capability of the integrated system to perform required functions during normal, shutdown, and accident situations. g. General Design Criterion 61 (GDC 61), as related to the system design for fuel 72 storage and handling of radioactive materials, including the following elements: (1) The capability for periodic testing of components important to safety. (2) Provisions for containment. (3) Provisions for decay heat removal. (4) The capability to prevent reduction in fuel storage coolant inventory under accident conditions in accordance with the guidelines of position C.6 of Regulatory Guide 1.13. 9.1.3-7 DRAFT Rev. 2 - April 1996 (5) The capability and capacity to remove corrosion products, radioactive materials and impurities from the pool water and reducing occupational exposures to radiation. h. General Design Criterion 63 (GDC 63), as it relates to monitoring systems 73 provided to detect conditions that could result in the loss of decay heat removal, to detect excessive radiation levels, and to initiate appropriate safety actions. i. 10 CFR Part 20, paragraph 20.1(c) 20.1101(b) as it