Document: NUREG-0800
Document ID: ecb92ac6-97df-4e4b-a20a-81638c2d573b
Document Type: srp
Title: - 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350157.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
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 flow rate, and flow rate from the reactor coolant system to the containment systems (if applicable) during the transient are reviewed. *The more important of these parameters (as listed in subsec- tion I of this'SRP section) are compared to those predicted for other similar plants to confim that they are within the expected range. The percentage of fuel rods that experience'failure is reviewed and AEB is notified regarding the extent of fuel failures predicted by the analysis. CPB is consulted regarding the acceptance criteria for fuel rod failure and core coolability. 15.3.3-5 Rev. 2 - July 1981 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). The staff concludes that the consequences of postulated rotor seizure or broken shaft events meet the requirements set forth in the General Design Criteria 27, 28, and 31 regarding control rod insertability and core coolability, 10 CFR Part 100 guidelines regarding radiological dose at the site boundary, and applicable TMI Action Plan items. This conclusion is based upon the following: (a) The applicant has demonstrated that the resultant fuel damage was limited such that control rod insertability would be maintained, and that no loss of core cooling capability resulted. The minimum departure from nucleate boiling ratio (DNBR) or critical power ratio (CPR) experienced by any fuel rod was , resulting in % of the rods experiencing cladding perforation. (b) The applicant met the requirements of GDC 31 with respect to demonstrating