Document: NUREG-0800
Document ID: fd06ef1f-75ea-4f29-9779-8714e92f3050
Document Type: srp
Title: MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070451.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.7
CFR Part: 
CFR Title: 

Content:
with GDC 4 requires that structures, systems, and components important to safety be designed to accommodate the effects of, and be compatible with, the environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, including LOCAs and the resulting dynamic effects. The requirements of GDC 4 are imposed on the MSIVLCS because this equipment must continue functioning during the post-LOCA recovery period in order to limit offsite radiation doses. Environmental conditions that may occur in association with either loss- of-coolant events or dynamic effects could compromise the function of the MSIVLCS. Regulatory Guide 1.96, positions C.2 and C.4, provides guidance on meeting this requirement with respect to the MSIVLCS. Meeting the requirements of GDC 4 provides assurance that the MSIVLCS will function, thereby ensuring that releases of fission products to the environment will not result in offsite doses in excess of those specified in 10 CFR Part 100.41 3. Compliance with GDC 54 requires that piping systems penetrating primary reactor containment be provided with leak detection, isolation, and performance testing capabilities. 6.7-7 DRAFT Rev. 3 - April 1996 The requirements of GDC 54 are imposed to provide assurance that unanticipated leakage from parts of the MSIVLCS that penetrate the reactor containment will not occur during the recovery period after a LOCA. Such leakage would compromise the ability of the system to limit the release of fission products to the environment. Regulatory Guide 1.96, positions C.3 and C.5 through C.12, provides guidance on meeting this requirement with respect to the MSIVLCS. Meeting the requirements of GDC 54 provides assurance that the MSIVLCS will not be a source of additional leakage of fission products and will not result in offsite doses in excess of those specified in 10 CFR Part 100.42 III. REVIEW PROCEDURES The procedures below are used during the standard design certification,