Document: NUREG-0800
Document ID: a52f76c0-2afc-4d48-b4c4-422dbb4cb298
Document Type: srp
Title: 2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350392.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.4
CFR Part: 
CFR Title: 

Content:
Rev. 1 - July 1981 The basic objectives of the review of the transients described above are: 1. To identify which of the transients are the most limiting. 2. To verify that, for the most limiting transient, the plant responds in such a way that the criteria regarding fuel damage and system pressure are met. The specific criteria necessary to meet the relevant requirements of the regula- tions identified above for incidents of moderate frequency are as follows: (a) Pressure in the reactor coolant and main steam systems should be maintained below 110% of the design Values (Ref. 2). (b) Fuel cladding integrity shall be maintained by ensuring that the minimum DNBR remaining above the 95/95 DNBR limit for PWRs and the CPR remains above the MCPR safety limit for BWRs based on acceptable correlations (see SRP Section 4.4). (c) An incident of moderate frequency should not generate a more serious plant condition without other faults occurring independently. (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 acci- dents, 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 mode (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) The requirements stated in Regulatory Guide 1.105, "Instrument Spans and Setpoints," are used with regard to their impact on the plant response to the type of transients addressed in this SRP section. (f) 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 should