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:
conditions in References 11 and 12. DRAFT Rev. 2 - April 1996 15.3.1-4 The basic objectives of the review of loss of forced reactor coolant flow transients are: 1. To identify which of the transients are the most limiting. 2. To verify that, for the most limiting transients, the plant responds to the loss of flow transients 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 GDC General Design Criteria 10, 15, and 26 for incidents of moderate frequency are: 32 a a. Pressure in the reactor coolant and main steam systems should be maintained below 110% of the design valvesvalues (Ref. 5). 33 b. Fuel-cladding integrity shall be maintained by ensuring that the minimum departure from nucleate boiling ratio (DNBR) remains above the 95/95 DNBR limit for PWRs and the critical power ratio (CPR) remains above the minimum critical power ratio (MCPR)34 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 accidents, the number of fuel failures 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. 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