Document: NUREG-0800
Document ID: 2c839e4a-a342-4e25-9a7c-82d678a0f754
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340657.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6
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Content:
policy to Inform the nuclear industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be reviser' periodically. as appropriate, to accommodate comments and to reflect new Informa- tior and experience. Comments and suggestions for improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Washington, D.C. 2O65. 7. The effectiveness of static and active heat removal mechanisms. 8. The pressure conditions within subcompartments and acting on system components and supports due to high energy line breaks, e.g., the sacrificial shield structure. 9. The range and accuracy of instrumentation that is provided to monitor and record containment conditions during and following an accident. 10. The suppression pool temperature limit during reactor coolant system safety/relief valve operation, including the events considered in analyzing suppression pool temperature response, assumptions used for the analyses, and suppression pool temperature monitoring system. 11. The reactor coolant system safety/relief valve in-plant confirmatory test program. 12. The evaluation of analytical models used for containment analysis. The CSB will coordinate other branch evaluations that interface with the overall review of the containment as follows: Instrumentation and Control Systems Branch (ICSB), as part of its primary responsibility for SRP Section 7.3, will evaluate the func- tional capability of the post-accident monitoring instrumentation and recording equipment. The Equipment Qualification Branch.(EQB), as part of its primary