Document: NUREG-0800
Document ID: 3e34268a-a6f4-4ce5-ba4d-7f2cec5a192e
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070481.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
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Content:
istrative controls to preclude inadvertent operation of the systems. If the containment is designed to withstand the maximum expected external pressure, the external design pressure of the containment should provide an adequate margin above the maximum expected external pressure to account for uncertainties in the analysis of the postulated event. 6.2.1.1.A-5 DRAFT Rev. 3 - April 1996 g. In accordance with the requirements of GDC 13 and 64, and 10 CFR 50.34(f)(2)(xvii) (for those applicants subject to 10 CFR 50.34(f)), instrumentation capable of operating 19 in the post-accident environment should be provided to monitor the containment atmosphere pressure and temperature and the sump water level and temperature following an accident. The instrumentation should have adequate range, accuracy, and response to assure that the above parameters can be tracked and recorded throughout the course of an accident. Item II.F.1 of NUREG-0737 and NUREG-0718 (References 24 and 25) , and Regulatory Guide 1.97, "Instrumentation For Light Water Cooled Nuclear 20 Power Plants to Assess Plant Conditions During and Following An Accident," should be followed. h. The minimum calculated containment pressure should not be less than that used in the analysis of the emergency core cooling system capability (See SRP Section 6.2.1.5, "Minimum Containment Pressure Analysis for Emergency Core Cooling System Performance Capability Studies"). i. Containment internal structures and system components (e.g., reactor vessel, pressurizer, steam generators) and supports should be designed to withstand the differential pressure loadings that may be imposed as a result of pipe breaks within the containment subcompartments (See SRP Section 6.2.1.2, "Subcompartment Analysis"). j. In meeting the requirements of 10 CFR 50, §50.34(f)(3)(v)(A)(1), applicants subject to this article should evaluate an accident that releases hydrogen generated from a 100% fuel clad metal-water reaction. The evaluation should