Document: NUREG-0800
Document ID: eb937958-fe7c-410a-91e3-63f04734878a
Document Type: srp
Title: MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM (BMR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350465.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.7
CFR Part: 
CFR Title: 

Content:
s to construct and operate nuclear power plants. These documents are made available to the public as part of the Commission's policy to inform the nuclear Industry and the general public of regulatory procedure sand 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 revised periodically, as appropriate, to accommodate comments and to reflect new Informa- tion 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. 2055 2. The ASB also reviews the design of the leakage control system with respect to the following: a. The capability of the system to withstand the effects of the safe shutdown earthquake, including the source of sealing medium, if any. b. The capability of the system to control main steam isolation valve leakage and preserve containment integrity under design basis LOCA conditions, including loss of offsite power. c. The compatibility of initiation means and controls of the system with loading requirements on the emergency electrical buses, operator reac- tion times, and with actuation'times available in view of the specified main steam isolation valve leakage limits. d. The requirements for interlocks to prevent inadvertent system operation. e. The capability of the system design to permit functional testing of components, controls, and actuation devices during power operations to the extent practicable and complete functional testing during plant shutdown. f. The capability of the system and main steam supply system components to withstand effects resulting from the use of a