Document: NUREG-0800
Document ID: 7b1d7632-755f-4dce-bb81-d95bded919e0
Document Type: srp
Title: 3
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350142.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.5.1
CFR Part: 
CFR Title: 

Content:
Rev. 1 - July 1981 d. An incident of moderate frequency in combination with any single active component failure, or single operator error, shall be considered and is an event for which an estimate of the number of potential fuel failures shall be provided for radiological dose calculations. For such accidents, fuel failure must be assumed for all rods for which the DNBR or CPR falls below those valves 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. e. To meet the requirements of General Design Criteria 10, 15 and 26 the guide- lines of 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. f. The most limiting plant systems single failure, as defined in the "Defini- tions and Explanations" of Appendix A to 10 CFR Part 50, shall be identi- fied and assumed in the analysis and shall satisfy the guidelines stated in Regulatory Guide 1.53 (Ref. 14). The applicant's analysis of events leading to an increase of reactor coolant inventory should be performed using an acceptable analytical model. The equa- tions, sensitivity studies, and models described in References 5 through 8 are acceptable. If other analytical methods are proposed by the applicant, these methods are evaluated by the staff for acceptability. For new generic methods, the reviewer initiates an evaluation. The values of parameters used in the analytical model should be suitably conserv- ative. 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 uncertainties, unless a lower power level can be