Document: NUREG-0800
Document ID: 0b17303b-e5cc-4091-b22c-056b0c78eb34
Document Type: srp
Title: – 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070707.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
eneral Electric Boiling Water Reactor," NEDP-10802, General Electric Company, April 1973. 13. General Electric Co., ODYNA - One Dimensional Dynamic Model (proprietary computer software for use in ABWR transient analysis to simulate pressurization events). 1 68 14. General Electric Co., REDYA (proprietary computer software for use in ABWR transient analysis to simulate other than pressurization events).69 15. CESEC-III (CENPD-107; LD-82-001). (Calculates system parameters such as core power, flow, pressure, temperature, and valve actions during a transient.)70 16. TORC (CENPD-161) and CETOP (CENPD-206-P-A). (TORC is used to simulate the three-dimensional fluid conditions within the reactor core. Results from TORC include the core radial distribution of the relative channel axial flow that is used to calibrate CETOP. TORC or CETOP calculations for the DNBR use the CE-1 critical heat flux correlation.) 15.3.3-13 DRAFT Rev. 3 - April 1996 17. HERMITE (CENPD-188-A). (HERMITE is used to determine short-term response of the reactor core during the postulated reactor coolant pump rotor-seizure event and total loss- of-flow event.) 18. COAST (SSAR; CENPD-98). (Calculates the time-dependent reactor coolant mass flow rate in each loop during reactor coolant pump coastdown transients.) 19. STRIKIN-II (CENPD-133; CENPD-135 Supps. 2 and 4). (Calculates the cladding and fuel temperatures for an average or hot fuel rod.) 20 NUREG-1465, "Accident Source Terms for Light-Water Nuclear Power Plants," February 1995.71 210. Standard Review Plan Section 4.4, "Thermal and Hydraulic Safety." 221. Standard Review Plan Section 4.2, "Fuel System Design." 232. Standard Review Plan Section 7.2, "Reactor Trip System." 243. Standard Review Plan Section 7.3, "Engineered Safety Features System." 254. Standard Review Plan Section 7.4, "Systems Required for Safe Shutdown." 265. Standard Review Plan Section 7.5, "Safety-Related Display Instrumentation." 17. 10 CFR Part 5, Appendix A, General Design