Document: NUREG-0800
Document ID: 7b7303eb-a3a7-433b-8301-fcaba03194ea
Document Type: srp
Title: - 15.1.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070676.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.1
CFR Part: 
CFR Title: 

Content:
-SAR-205," Babcock & Wilcox Company, February 1974. 9. General Design Criterion 10, "Reactor Design." 10. General Design Criterion 15, "Reactor Coolant System Design." 11. General Design Criterion 20, "Protection System Functions."67 1112. General Design Criterion 26, "Reactivity Control System Redundancy and 68 Capability." 1213. Regulatory Guide 1.53, "Application of the Single Failure Criterion to Nuclear Power Plant Systems Protection." 1314. Regulatory Guide 1.105, "Instrument Spans and Setpoints." 1415. NUREG-0660, "NRC Action Plan Developed as a Result of the TMI-2 Accident." 1516. NUREG-0718, "Licensing Requirements for Pending Applications for Construction Permits and Manufacturing Licenses." 17. General Electric Company, ODYNA - One Dimensional Dynamic Model (proprietary computer software for use in ABWR transient analysis to simulate pressurization events). ** 69 18. General Electric Company, REDYA (proprietary computer software for use in ABWR transient analysis to simulate other than pressurization events).70 19. CESEC-III (CENPD-107; LD-82-001). (Calculates system parameters such as core power, flow, pressure, temperature, and valve actions during a transient.)71 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 is used for DNBR calculations using the CE-1 critical heat flux correlation.)72 15.1.1-13 DRAFT Rev. 2 - April 1996 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.)73 22. COAST (SSAR; CENPD-98). (Calculates the time-dependent reactor coolant mass flow rate in each loop during reactor coolant pump coastdown transients.)74 23. STRIKIN-II (CENPD-133; CENPD-135 Supps. 2 and 4).