Document: NUREG-0800
Document ID: 621763b9-bd48-4ded-8c42-b942a23a06d4
Document Type: srp
Title: – 15.2.5
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070680.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.1
CFR Part: 
CFR Title: 

Content:
evaluation of conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.56 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." In Generic Letter 81-08, dated January 29, 1981, all BWR licensees and applicants were 3 informed that transient analyses performed by the General Electric Company (GE) supporting 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 ABWR standard design. These modified codes, ODYNA and REDYA, have been reviewed by the NRC staff and approved for design analysis of the ABWR. DRAFT Rev. 2 - April 1996 15.2.1-12 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. General Electric Company, ODYNA - One Dimensional