Document: NUREG-0800
Document ID: 3ea2f0ac-4d7e-464a-b1c4-390c3970f642
Document Type: srp
Title: provides specific thermal-hydraulic criteria.  The available radioactive fission product
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070740002.pdf
Revision Date: 2023-06
Chapter: 4
Section ID: 4.4
CFR Part: 
CFR Title: 

Content:
ssion Gas Behavior in Water Reactor Fuels - Seminar Proceedings Cadarache, France, 26-29, September 2000. PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50 and 10 CFR Part 52, and were approved by the Office of Management and Budget, approval number 3150-0011 and 3150-0151. PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number. 4.2-29 Revision 3 - March 2007 APPENDIX A EVALUATION OF FUEL ASSEMBLY STRUCTURAL RESPONSE TO EXTERNALLY APPLIED FORCES I. BACKGROUND Earthquakes and postulated pipe breaks in the reactor coolant system would result in external forces on the fuel assembly. SRP Section 4.2 states that fuel system coolability should be maintained and that damage should not be so severe as to prevent control rod insertion when required during these low probability accidents. This appendix describes the review that should be performed of the fuel assembly structural response to seismic and LOCA loads. NUREG- 0609, NUREG/CR-1018, NUREG/CR-1019, and NUREG/CR-1020 provide background material for this appendix. II. ANALYSIS OF LOADS 1. Input Input for the fuel assembly structural analysis comes from the results of the primary coolant system and reactor internals structural analysis, which is reviewed by the organization responsible for the review of mechanical engineering issues. Input for the fuel assembly response to a LOCA should include (1) motions of the core plate, core shroud, fuel alignment plate, or other relevant structures (these motions should correspond to the break that produced the peak fuel assembly loadings in the primary coolant system and reactor internals analysis) and (2) transient pressure differences that apply loads directly to the fuel assembly. If