Document: NUREG-0800
Document ID: 73a7c7ff-f0ac-467b-ba1d-0fb71e328868
Document Type: srp
Title: examines this margin to ensure that specified acceptable fuel design limits are not
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070705.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.2
CFR Part: 
CFR Title: 

Content:
he Design of Stationary Pressurized Water Reactor Plants," American National Standards Institute (1974). 121. ANS Trial Use Standard N212, "Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants," American Nuclear Society (1974). 132. Standard Review Plan Section 4.2, "Fuel System Design." 143. Standard Review Plan Section 4.4, "Thermal and Hydraulic Safety." 154. Standard Review Plan Section 7.2, "Reactor Trip System." 165. Standard Review Plan Section 7.3, "Engineered Safety Features System." 176. Standard Review Plan Section 7.4, "Systems Required for Safe Shutdown." 187. Standard Review Plan Section 7.5, "Safety-Related Display Instrumentation." 19. CESEC-III (CENPD-107; LD-82-001). (Calculates system parameters such as core power, flow, pressure, temperature, and valve actions during a transient.)80 20. 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 DNBR use the CE-1 critical heat flux correlation.)81 21. 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.)82 22. COAST (SSAR; CENPD-98). (Calculates the time-dependent reactor coolant mass flow rate in each loop during reactor coolant pump coastdown transients.)83 In Generic Letter 81-08, dated January 29, 1981, all BWR licensees and applicants c were informed that transient analyses performed by the General Electric Company (GE) to support reload submittal received after February 1, 1981, must contain appropriate ODYN analyses in place of those previously performed with REDY for the limiting transients. These codes have since been modified by GE for use in the analysis of limiting transients on the standard design