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:
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 necessary to meet the TMI Action Plan requirements task action plan items of NUREG-0718 and -0737 (Ref. 6 and 7) are as follows: 60 1. An evaluation of ECCS performance has been performed by the applicant in accordance with an approved evaluation model that satisfies the requirements of 10 CFR Part 50, 61 § 50.46. Regulatory Guide 1.157 and Section I of Appendix K to 10 CFR Part 50 62 provide guidance on acceptable evaluation models. For the full spectrum of reactor 63 coolant pipe breaks, and taking into consideration requirements for reactor coolant pump operation during a small break loss-of-coolant accident, (Refs. 10, 11, and 12) the 64 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 1200 C (2200 F) . o o 65 b. The calculated total oxidation of the cladding does not exceed 17% of the total cladding thickness before oxidation. DRAFT Rev. 3 - April 1996 15.6.5-6 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.