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:
the requirements of GDC General Design Criteria 10, 70 17 and 26 with respect to demonstrating that the specified acceptable fuel design 71 limits are not exceeded for this event. This requirement has been met since the results of the analysis showed that the thermal margin limits (MDNBRminimum departure from nucleate boiling ratio for PWRs pressurized water reactors and MCPR minimum critical power ratio for BWRs boiling water reactors) are 72 satisfied as indicated by SRP Section 4.4. 2. The applicant has met the requirements of General Design Criterion GDC 15 73 and 17 with respect to demonstrating that the reactor coolant pressure boundary 74 limits have not been exceeded for this event. This requirement has been met DRAFT Rev. 2 - April 1996 15.3.1-10 since the analysis showed that the maximum pressure of the reactor coolant and main steam systems did not exceed 110% of the design pressure. 3. The applicant has met the requirements of General Design Criterion GDC 26 75 with respect to the capability of the reactivity control system to provide adequate control of reactivity during this event while including appropriate margin for stuck rods since the specific acceptable fuel design limits were not exceeded. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff’s evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.76 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 77 cases in which the applicant proposes