Document: NUREG-0800
Document ID: 94ab38ac-ddfc-4ba1-ae38-bc25ffa6e976
Document Type: srp
Title: – 15.4.5
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070716.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.4.4
CFR Part: 
CFR Title: 

Content:
ce criteria are based on meeting the relevant requirements of the following regulations: A. General Design Criteria (GDC) 10 (GDC 10) and 20 (GDC 20) as itthey relates to the 16 reactor coolant system being designed with appropriate margin to assureensure that specified acceptable fuel design limits are not exceeded during normal operations, including anticipated operational occurrencesAOOs. B. General Design Criteria 15 (GDC 15) and 28 (GDC 28) as itthey relates to the reactor 17 coolant system and its associated auxiliaries being designed with appropriate margin to assureensure that the pressure boundary will not be breached during normal operations, including anticipated operational occurrencesAOOs. C. General Design Criterion 26 (GDC 26) as it relates to the reliable control of reactivity 18 changes to assureensure that specified acceptable fuel design limits are not exceeded, including anticipated operational occurrencesAOOs. This is accomplished by DRAFT Rev. 2 - April 1996 15.4.4-4 assuringensuring that appropriate margin for malfunctions, such as stuck rods, is accounted for. The basic objectives of the review of the transientsAOOs described above are: 1. To identify which of the transientsAOOs are the most limiting. 2. To verify that, for the most limiting transientAOOs, the plant responds in such a way that the criteria regarding fuel damage and system pressure are met. The specific criteria necessary to meet the relevant requirements of the regulations identified above for incidents of moderate frequency are as follows: (a) Pressure in the reactor coolant and main steam systems should be maintained below 110% of the design values (Ref. 2ASME Boiler and Pressure Vessel Code, Section III, Article NB-7000 ). 19 (b) Fuel-cladding integrity shall be maintained by ensuring that the minimum departure from nucleate boiling ratio (DNBR) remains above the 95/95 DNBR 20 limit for PWRs and the critical power ratio (CPR) remains above the minimum 21 critical power