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:
ch accidents, fuel failure must be assumed for all rods for which the DNBR or CPR falls below those values cited above for cladding integrity unless it can be shown, based on an acceptable fuel damage model (see SRP Section 4.2) that fewer failures occur. There shall be no loss of function of any fission product barrier other than the fuel cladding. 5. To meet the requirements of General Design Criteria 10, 15, 20, and 26 the positions of 30 Regulatory Guide 1.105, "Instrument Spans and Setpoints," are used with regard to their impact on the plant response to the type of transient addressed in this SRP section. 15.1.1-5 DRAFT Rev. 2 - April 1996 6. The most limiting plant systems single failure, as defined in the "Definitions and Explanations" of Appendix A to 10 CFR Part 50, shall be identified and assumed in the analysis and shall satisfy the positions of Regulatory Guide 1.53 (Ref. 12).31 The applicant's analysis of transients caused by excessive heat removal should be performed using an acceptable analytical model. The equations, sensitivity studies, and models described in References 5 through 8 are acceptable. BWR and ABWR pressurization events should be evaluated using the models provided in References 28 and 17, respectively. Reference 18 provides acceptable models for analysis of other (non-pressurization) transients for the ABWR. 32 References 19 through 23 are acceptable models for non-LOCA transient analysis for CE80+ applications. If other analytical methods are proposed by the applicant, these methods are 33 evaluated by the staff for acceptability. For new generic methods, the reviewer initiates an evaluation. The values of the parameters used in the analytical model should be suitably conservative. The following values are considered acceptable for use in the model: a. The initial power level is taken as the licensed core thermal power for the number of loops initially assumed to be operating plus an allowance of 2% to account for power measurement