Document: NUREG-0800
Document ID: 1085af08-a4b7-4fe7-bfed-ca7a60f2022c
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070734.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
accident and that the control rods can also be inserted. 8. The MEBEMEB also evaluates the effects of blowdown loads on the piping of the 51 reactor coolant system and on the support structures of the components of the reactor coolant system. Upon request from RSBSRXB, MEBEMEB verifies that acceptable 52 53 criteria (Ref. 5) have been employed in the design of the reactor coolant system and its supports to prevent failures of the reactor coolant pressure boundary and engineered safety feature equipment in the event of a LOCA. 15.6.5-5 DRAFT Rev. 3 - April 1996 9. The Human Factors Assessment Branch (HHFB) evaluates plant operating procedures as a part of its review of SRP Section 13.5.2. Upon request from SRXB, HHFB verifies that the plant operating procedures include actions relative to reactor coolant pump trip following small break loss-of-coolant accidents that are based on plant-specific safety evaluations.54 For those areas of review identified above as being reviewed as part of the primary review responsibility of other branches, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP section of the corresponding primary branch. II. ACCEPTANCE CRITERIA RSB acceptance criteria areAcceptance is based on meeting the relevant requirements of the 55 following regulations: aA. 10 CFR Part 50, § 50.46 and Appendix K as it relates to ECCS equipment being 56 57 provided that refills the vessel in a timely manner for a loss-of-coolant accident resulting from a spectrum of postulated piping breaks within the reactor coolant pressure boundary. bB. General Design Criterion (GDC) 35 as it relates to redundant ECCS components being 58 provided to adequately cool the core during a loss-of-coolant accident. cC. 10 CFR Part 100 (Ref. 4) as it relates to mitigating the radiological consequences of an 59 accident. Specific criteria necessary to meet the relevant requirements of the regulations identified above and