Document: NUREG-0800
Document ID: f885abea-c146-404b-b0f6-c4ded333294f
Document Type: srp
Title: SPENT FUEL STORAGE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070503.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.1.2
CFR Part: 
CFR Title: 

Content:
ared structures, systems, and 43 components important to safety being capable of performing required safety functions. 4. General Design Criterion 61 (GDC 61), as it relates to the facility design for fuel storage 44 and handling of radioactive materials. Acceptance for meeting this criterion is based on conformance to positions C.1 and C.4 of Regulatory Guide 1.13 and the appropriate paragraphs of ANS 57.2. Acceptance is also based on meeting the fuel storage capacity requirements noted in subsection III.1 of this SRP section. 5. General Design Criterion 62 (GDC 62), as it relates to the prevention of criticality by 45 physical systems or processes utilizing geometrically safe configurations. Acceptance for meeting this criterion is based on conformance to positions C.1 and C.4 of Regulatory Guide 1.13 and the appropriate paragraphs of ANS 57.2. 6. General Design Criterion 63 (GDC 63), as it relates to monitoring systems provided to 46 detect conditions that could result in the loss of decay heat removal capabilities, to detect excessive radiation levels, and to initiate appropriate safety actions. Acceptance for meeting this criterion is based on conformance with paragraph 5.4 of ANS 57.2. Technical Rationale47 The technical rationale for application of these acceptance criteria to reviewing spent fuel storage is discussed in the following paragraphs:48 1. Compliance with GDC 2 requires that nuclear power plant structures, systems, and components important to safety be designed to withstand the effects of natural phenomena such as earthquake, tornado, hurricane, flood, tsunami and seiche without loss of capability to perform their safety functions. The function of the spent fuel storage facility is to maintain spent fuel in a subcritical array that can be adequately cooled during all credible storage conditions and to limit offsite exposures in the event of significant release of radioactive materials from the fuel. The requirements of GDC 2 are imposed to verify