Document: NUREG-0800
Document ID: 73a7c7ff-f0ac-467b-ba1d-0fb71e328868
Document Type: srp
Title: examines this margin to ensure that specified acceptable fuel design limits are not
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070705.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.2
CFR Part: 
CFR Title: 

Content:
ed model. The values of system parameters and initial core and system conditions used as input to the model are reviewed by the RSBSRXB. Of particular importance are the reactivity coefficients 58 and control rod worths used by the applicant's in his analysis and the variation of moderator 59 temperature, void, and Doppler coefficients of reactivity with core life. The justification provided by the applicant to show that the applicant he has selected the core burnup that yields 60 the minimum margins is evaluated. CPB is consulted regarding SRXB reviews the values of 61 the reactivity parameters used in the applicant's analysis. The results of the analysis are reviewed and compared with the acceptance criteria presented in subsection II of this SRP section regarding the maximum pressure in the reactor coolant and main steam systems. The temporal changes of the neutron power, heat fluxes (average and maximum), reactor coolant system pressure, minimum DNBR (PWR) or CPR (BWR), core and recirculation loop coolant flow rates (BWR), coolant conditions (inlet temperature, core average temperature (PWR), core average steam volume fraction (BWR), average exit and hot channel exit temperatures, and steam fractions), steam line pressure, containment pressure, pressure relief valve flow rate, and flow rate from the reactor coolant system to the containment systems (if applicable) during the transient are reviewed. The important parameters for the loss of reactor coolant flow transients are compared to those predicted for other similar plants to verify that they are within the expected range. Note: In the Final Safety Evaluation Report for the Advanced Boiling Water Reactor (ABWR)(Reference 26), the staff allowed an exception to Acceptance Criterion II.A for the postulated trip of all reactor internal pumps (RIPs) with offsite power available. Normally, such transients are treated as anticipated operational occurrences, which must not result in specified acceptable fuel design