Document: NUREG-0800
Document ID: d967feb0-b1b1-4bfb-a8b4-1d6ce45e13a2
Document Type: srp
Title: 4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350154.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.1
CFR Part: 
CFR Title: 

Content:
ler coef- ficients of reactivity with core life. The justification provided by the applicant to show that he has selected the core burnup that yields the minimum margins is evaluated. CPB is consulted regarding the values of the reactivity parameters used in the applicant's analysis. The results of the analysis are reviewed and compared to the acceptance criteria presented in subsection 11 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 temper- ature (PWR), core average steam volume fraction (BWR),'average exit and hot channel exit temperatures, and steam fractions), steamline pressure, contain- ment pressure, pressure relief valve flowrate, 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. CPB is consulted regarding the specified acceptable fuel design limits (SAFDLs). AEB is notified regarding the extent of fuel failures predicted by the analysis if SAFDLs are exceeded. The PTRB review confirms that a commitment has been made in the SAR to conduct preoperational tests to verify flow coastdown calculations. IV. EVALUATION FINDINGS The reviewer verifies that the SAR contains sufficient information and his review supports the following kinds of statements and conclusions which should be included in the staff's safety evaluation report (SER): 15. 3. 1-5 Rev. 1 - July 1981 Several types of plant occurrences can result in an unplanned decrease in reactor coolant flow rate. The ones expected during the life of the plant are