Document: NUREG-0800
Document ID: e6b7e6d3-a99d-424d-bfa0-491bc48f46cf
Document Type: srp
Title: ISOLATION CONDENSER SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0708/ML070810517.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.13
CFR Part: 
CFR Title: 

Content:
hat: 1) the maximum fuel element cladding temperature shall not exceed 2200EF, 2) the maximum total cladding oxidation shall nowhere exceed 0.17 times the total cladding thickness before oxidation, 3) the total amount of hydrogen generated from the chemical reaction of the cladding with water or steam shall not exceed 0.01 times 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, 4) changes in core geometry shall be such that the core remains amenable to cooling, and 5) after any calculated successful initial operation of the ECCS, the calculated core temperature shall be maintained at an acceptable low value and decay heat shall be removed for the extended period of time required by the long-lived radioactivity remaining in the core. 12. For 10 CFR 50.63, the application should demonstrate compliance with RG 1.155, which identifies acceptable methods to support the plant’s ability to withstand for a specified duration and recover from an SBO. 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 GDC 2 requires that nuclear power plant SSCs important to safety be designed to withstand the effects of seismic events and other natural phenomena without losing their capability to perform their safety functions. The subject SSCs are those necessary to ensure (1) the integrity of the reactor coolant pressure boundary, (2) the capability to shut down the reactor and maintain it in a safe-shutdown condition, or (3) the capability to prevent or mitigate the consequences of accidents that could result in potential offsite exposures comparable to the guideline exposures of 10 CFR Part 100. Because the ICS performs ECCS functions, the ICS, and structures housing the ICS, must be capable of