Document: NUREG-0800
Document ID: 0b17303b-e5cc-4091-b22c-056b0c78eb34
Document Type: srp
Title: – 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070707.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
erience failure is reviewed and AEBPERB is 53 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.54 DRAFT Rev. 3 - April 1996 15.3.3-10 For standard design certification reviews under 10 CFR Part 52, the procedures above should be followed, as modified by the procedures in SRP Section 14.3 (proposed), to verify that the design set forth in the standard safety analysis report, including inspections, tests, analysis, and acceptance criteria (ITAAC), site interface requirements and combined license action items, meet the acceptance criteria given in subsection II. SRP Section 14.3 (proposed) contains procedures for the review of certified design material (CDM) for the standard design, including the site parameters, interface criteria, and ITAAC.55 IV. EVALUATION FINDINGS The reviewer verifies that the SAR contains sufficient information and that the review supports 56 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 17, 27, 28, and 31 regarding the 57 ability to insert control rods insertability and to cool the core coolability, and 10 CFR Part 100 58 guidelines regarding radiological dose at the site boundary, and applicable TMI Action Plan items. This conclusion is based upon the following: 59 (a) The applicant has demonstrated that the resultant fuel damage was limited such that the ability to insert control rods insertability would be maintained, and that no loss of core 60 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