Document: NUREG-0800
Document ID: 598d070d-fb96-43ce-ad4f-27f14623be46
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350119.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15
CFR Part: 
CFR Title: 

Content:
ith Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES 1. Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." 2. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," Article NB-7000, "Protection Against Overpressure," American Society of Mechanical Engineers. 3. Regulatory Guide 1.105, "Instrument Spans and Setpoints." 4. "Qualification of the One-Dimensional Core Transient Model for Boiling Water Reactors," General Electric Reports NEDO-24154 and NEDE-24154P Volumes I, II, and III, October 1978. 5. "Loftran Code Description," Westinghouse Electric Corporation Report WCAP-7907, October 1972 (in review). 6. "CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam Supply System," CENPD-107, April 1974 (in review). 7. "TRAP2-Fortran Program for Digital Simulation of the Transient Behavior of the Once-Through Steam Generator and Associated Reactor Coolant Systems," Babcock & Wilcox, BAW-10128, August 1976 (in review). 8. ANSI N18.2, "Nuclear Safety Criteria for the Design of Stationary Pres- surized Water Reactor Plants," American National Standards Institute (1974). 9. ANS Trial Use Standard N212, "Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants," American Nuclear Society (1974). 15.2.1-7 Rev. 1 - July 1981 10. 10 CFR Part 50, General Design Criterion 10, "Reactor Design." 11. 10 CFR Part 50, General Design Criterion 15, "Reactor Coolant System Design." 12. 10 CFR Part 50, General Design Criterion 26, "Reactivity Control System Redundancy and Capability." 15.2.1-8 Rev. 1 - July 1981