Document: NUREG-0800
Document ID: 931b933f-eeb8-4e82-b76a-4813dde9214a
Document Type: srp
Title: SPENT FUEL POOL COOLING AND CLEANUP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190013.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.1.3
CFR Part: 
CFR Title: 

Content:
ceptance is based on meeting position C.2 of RG 1.13. This criterion does not apply to the cleanup system and need not apply to the cooling water system if the makeup system, its source, the building, and its ventilation and filtration system are tornado protected, and the ventilation and filtration system meets the guidelines of RG 1.52. 3. GDC 5 as related to shared systems and components important to safety being capable of performing required safety functions. 4. GDC 61 as related to the system design for fuel storage and handling of radioactive materials, including the following elements: A. The capability for periodic testing of components important to safety. B. Provisions for containment. C. Provisions for decay heat removal that reflect its importance to safety. 9.1.3-5 Revision 2 - March 2007 D. The capability to prevent reduction in fuel storage coolant inventory under accident conditions. E. The capability and capacity to remove corrosion products, radioactive materials and impurities from the pool water and reduce occupational exposures to radiation. 5. GDC 63 as it relates to monitoring systems 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. 6. 10 CFR 20.1101(b) as it relates to radiation doses being kept as low as is reasonably achievable (ALARA). In meeting this regulation, RG 8.8, positions C.2.f(2) and C.2.f(3) can be used as a basis for acceptance. 7. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed inspections, tests, analyses, and acceptance criteria (ITAAC) that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the design certification is built and will operate in accordance with the design certification, the provisions of the Atomic Energy Act, and the NRC’s regulations.