Document: NUREG-0800
Document ID: ff35052f-d051-4098-a352-1e382f87365a
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340655.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
CFR Part: 
CFR Title: 

Content:
e spectrum of postulated reactor coolant system pipe breaks, and should be about 35 square feet or greater. 4. In meeting the requirements of General Design Criteria 39 and 40 regarding the inspection and testing of containment heat removal systems, the design of the ice condenser system and return fan system should incorporate pro- visions for periodic inservice inspection and testing of essential system components; e.g., the ice baskets and doors, the ice condenser temperature monitoring system, the available mass of ice, and return air fan performance and controls. 5. In meeting the requirements of General Design Criterion 16 regarding the containment design conditions important to safety, inadvertent operation of engineered safety features (e.g., the return air fan system or the containment spray system) should not cause the external design pressure of the primary containment to be exceeded. This may be accomplished through conservative containment design, use of vacuum relief devices, or electrical interlocks that preclude inadvertent operation of the spray and fan systems. 6. In meeting the requirements of General Design Criteria 13 and 64, instru- mentation capable of operating 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 instru- mentation should have adequate range, accuracy, and response to assure that the above parameters can be tracked and recorded throughout the course 6.2.1.1.B-4 Rev. 2 - July 1981 of an accident. Item II.F.1 of NUREG-0737 and NUREG-0718, and Regulatory Guide 1.97, "Instrumentation For Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," should be followed. 7. The minimum calculated containment pressure as determined by the LOTIC-2 Code (Ref. 26) should not be less than that used in the analysis of the emergency core cooling system capability (see SRP