Document: NUREG-0800
Document ID: 73747cf4-ff95-449b-b6b0-53dc0755b9e0
Document Type: srp
Title: OTHER SEISMIC CATEGORY I STRUCTURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1235/ML12353A382.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.4
CFR Part: 
CFR Title: 

Content:
liner may be perforated, the applicant should indicate the provisions for avoiding leakage of radioactive water from the pool. B. Fuel Handling - The organization responsible for postulation of a drop accident and quantification of the drop parameters reviews the criteria related to fuel handling. The findings of the review are evaluated for the purpose of integrity of the racks and the fuel pool, including the fuel pool liner, in view of a postulated fuel-handling accident. The applicant should provide sketches and sufficient details of the fuel-handling system to facilitate this review. 3.8.4-30 Draft Revision 4 – December 2012 2. Applicable Codes, Standards, and Specifications Construction materials should conform to American Society of Mechanical Engineers, (ASME), Boiler and Pressure Vessel Code, (Code), Section III, Division 1, Subsection NF. All materials should be selected to be compatible with the fuel pool environment to minimize corrosion and galvanic effects. Design, fabrication, and installation of spent fuel racks of stainless steel material may be performed based on ASME Code, Section III, Division 1, Subsection NF requirements for Class 3 component supports. 3. Seismic and Impact Loads For new plants, dynamic input data such as floor response spectra or ground response spectra are developed using the criteria described in SRP Section 3.7. For operating plants where dynamic data are available (e.g., ground response spectra for a fuel pool supported by the ground, floor response spectra for fuel pools supported on soil where SSI was considered in the pool design, or a floor response spectra for a fuel pool supported by the reactor building), the design and analysis of a replacement rack system may be performed using the existing plant seismic design basis. As an alternate, the seismic analysis of spent fuel pool racks may be conducted using an updated plant seismic design basis developed using the criteria described in SRP Section 3.7. . For