Document: NUREG-0800
Document ID: 47c0ffe8-0c76-4d7a-8671-f04b7c8ae803
Document Type: srp
Title: – 15.3.2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070705.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.1
CFR Part: 
CFR Title: 

Content:
fuel cladding. The applicant's analysis of the loss of reactor coolant flow transients should use an acceptable analytical model. The equations, sensitivity studies, and models described in References 7 through 10 are acceptable. References 19 through 23 are acceptable computer codes for transient analyses of CE80+ applications that do not involve loss-of-coolant accidents (LOCAs). References 24 and 25 are acceptable transient analysis computer codes for design 35 analysis of the ABWR. If other analytical methods are proposed by the applicant, these 36 methods are evaluated by the staff for acceptability. For new generic methods, the reviewer requestsinitiates an evaluation byfor CPBSRXB.37 15.3.1-5 DRAFT Rev. 2 - April 1996 The values of parameters used in the analytical model wouldshould be suitably conservative. 38 The following values are considered acceptable for use in the model: a. The reactor is initially at rated output (licensed core thermal power) for the number of loops assumed operating, plus 2% to account for power measurement uncertainty, unless a lower power level can be justified by the applicant. The number of loops operating at the initiation of the event should correspond to the operating condition which maximizes the consequences of the event. b. Conservative scram characteristics are assumed, i.e., for a PWR maximum time delay with the most reactive rod held out of the core and for a BWR a design conservatism factor of 0.8 times the calculated negative reactivity insertion rate. c. The core burnup is selected to yield the most limiting combination of moderator temperature coefficient, void coefficient, Doppler coefficient, axial power profile, and radial power distribution. Technical Rationale The technical rationale for application of these acceptance criteria to transients involving loss of flow is discussed in the following paragraphs:39 a. Compliance with GDC 10 requires that the reactor core and associated coolant, control, and protection