Document: NUREG-0800
Document ID: 02fef38f-79ed-4d55-825f-81551bcfdcdc
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550016.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
arameters and assumptions used for the calculations were conservatively chosen, including the following points: 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 level of uncertainty 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. The maximum linear heat generation rate used should be based on the proposed licensed core thermal power as discussed in Item A and the technical specification limit on peaking factors, or on the technical specification limits on maximum linear heat generation rate. For many plants these limits may also be found in Technical Specification 5.6.5, Core Operating Limits Report (COLR). C. All permitted axial power shapes, as given in Section 4.3 of the SRP, should be addressed by the analyses. Normally, the evaluation model will identify the least favorable axial shape as a function of break size. If the evaluation model did not discuss axial shapes, or the discussion is not applicable to a given case, sensitivity studies are requested. D. The initial stored energy was conservatively calculated by the applicant. The value used is checked against the applicant's steady-state temperatures, as given in SRP Section 4.4, similar calculations performed by the staff, or calculations done for similar plants by previous applicants. E. Appropriate analyses are presented to support any credit taken for control rod insertion. 15.6.5-10 Revision 3 - March 2007 F. The applicant's analysis conservatively addresses the operation of the reactor coolant pump including requirements for reactor coolant pump trip during small break LOCAs as required by Generic Letters 85-012, 86-005, and 86-006. G. The analysis of boric acid precipitation should include a