Document: NUREG-0800
Document ID: 8940dd69-2a01-4786-bbe6-f71794a60643
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF POSTULATED PIPING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350156.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
ostulated piping breaks within the reactor coolant pressure boundary. 15.6.5-3 Rev. 2 - July 1981 b. General Design Criterion 35 as it relates to redundant ECCS components being provided to adequately cool. the core during alloss-of-coolant accident. c, 10 CFR Part 100 (Ref. 4) as it relates to mitigating the radiological consequences of an accident. Specific criteria necessary to meet the relevant requirements of the regulations identified above and necessary to meet task action plan items of NUREG-0718 and -0737 (Ref. 6 and 7) are as follows: 1. An evaluation of ECCS performance has been performed by the applicant in accordance with an approved evaluation model that satisfies the require- ments of 10. CFR Part 50, §50.46 and Appendix K to 10 CFR Part 50. For the full spectrum of reactor coolant pipe -breaks, the results of the evaluation must show that the specific requirements of the acceptance criteria for ECCS are satisfied as given below: a. The calculated maximum fuel element cladding temperature does not exceed 22000F. b. The calculated total oxidation of the cladding does not exceed 17% of the total cladding thickness before oxidation. c. The calculated total amount of hydrogen generated from the chemical reaction of the cladding with water or steam does not exceed 1% of the hypothetical amount that would be generated if all of the metal in the cladding cylinders surrounding the fuel, excluding the cladding surrounding the plenum volume, were to react. d. Calculated changes in core geometry are such that the core remains amenable to cooling. e. After any calculated successful initial operation of the ECCS, the calculated core temperature is maintained at an acceptably low value and decay heat is removed for the extended period of time required by the long-lived radioactivity. 2. The radiological consequences of the most severe LOCA are within the guidelines of 10 CFR Part 100. Appendices A, B and D to this SRP section provides the results of the LOCA