Document: NUREG-0800
Document ID: 02fef38f-79ed-4d55-825f-81551bcfdcdc
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550016.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
oxidation of the cladding does not exceed 17% of the total cladding thickness before oxidation. Total local oxidation includes pre-accident oxidation as well as oxidation that occurs during the course of the accident. 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. 15.6.5-7 Revision 3 - March 2007 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 and 10 CFR 100 or 10 CFR 50.67. For applications under 10 CFR Part 52, reviewers should use SRP Section 15.0.3, “Radiological Consequences of Design Basis Accidents - for ESP, DC and COL Applications.” 3. The TMI Action Plan requirements for II.E.2.3, II.K.2.8, II.K.3.5, II.K.3.25, II.K.3.30, II.K.3.31, and II.K.3.40 have been met. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. Compliance with 10 CFR 50.46 requires that light water cooled nuclear power reactors be equipped with an emergency core cooling system designed so that core performance following postulated loss-of-coolant accidents conforms to specified criteria related to limiting core damage. The requirements specified in 10 CFR 50.46 provide an acceptable and conservative means of calculation of the consequences of LOCAs from a spectrum of pipe break sizes and locations that have been subject