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
CFR Part: 
CFR Title: 

Content:
. 3. General Design Criterion 38, as it relates to the containment heat removal system(s) function to rapidly reduce the containment pressure and temperature following any loss-of-coolant accident and maintain them at acceptably low levels. 4. General Design Criterion 13, as it relates to instrumentation and control, requires instrumentation be provided to monitor variables and systems over their anticipated ranges for normal operation and for accident conditions as appropriate to assure adequate safety. 5. General Design Criterion 64, as it relates to monitoring radioactivity releases, requires means be provided for monitoring the reactor containment atmosphere for radioactivity that may be released from normal operations and from postulated accidents. 6. For those applicants subject to 10 CFR 50, § 50.34(f): a. 10 CFR 50, §50.34(f)(3)(v)(A)(1) as it relates to containment integrity being maintained during an accident that releases hydrogen generated from a 100- percent fuel clad metal-water reaction accompanied by either hydrogen burning or the added pressure from post accident inerting.14 b. 10 CFR 50, §50.34(f)(3)(v)(B)(1) as it relates to containment integrity being maintained during inadvertent full actuation of the post-accident inerting system, if installed.15 Specific criterion or criteria that pertain to design and functional capability of PWR dry containment, including subatmospheric containments that are used to meet the relevant requirements of the regulations are as follows: a. To satisfy the requirements of GDC 16 and 50 regarding sufficient design margin, for plants at the construction permit (CP) stage of review, the containment design pressure should provide at least a 10% margin above the accepted peak calculated containment pressure following a loss-of-coolant accident, or a steam or feedwater line break. For plants at the operating license (OL) stage of review, the peak calculated containment pressure following a loss-of-coolant accident, or