Document: NUREG-0800
Document ID: ff5838f8-986a-4d8b-a039-fb26df280426
Document Type: srp
Title: – 15.5.2
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070725.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.5.1
CFR Part: 
CFR Title: 

Content:
e neutron 61 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 62 line pressure, containment pressure, pressure relief valve flow rate, and flow rate from the reactor coolant system to the containment system (if applicable) are reviewed. The values of the more important of these parameters for the events leading to an increase in reactor coolant inventory are compared to with those predicted for other similar plants to confirm that they are within the expected range. Note: In the Final Safety Evaluation Report for the Advanced Boiling Water Reactor (ABWR) (Reference 9), the staff allowed an exception to Acceptance Criterion II.A for the postulated downscale failure of steam pressure regulator. Normally, such transients are treated as anticipated operational occurrences, which must not result in specified acceptable fuel design limits being exceeded. For this special case, the transient, requiring coincident failure of three independent channels, is not expected to occur during the lifetime of the plant and is not classified as an anticipated operational occurrence, but rather as an anticipated transient involving a common-mode software The SER draft should present one statement for all similar transients. ** 15.5.1-9 DRAFT Rev. 2 - April 1996 failure. Accordingly, the following criterion for the radiological dose calculation was established: the resulting dose due to fuel failures should not exceed 10 percent of 10 CFR Part 100, which is considered appropriate for an event of such frequency because of the unique design features of ABWR instrumentation and control systems.63 For standard design certification reviews under 10 CFR Part 52, the procedures above should be