Document: NUREG-0800
Document ID: 9697248b-d015-42be-8808-2202db24977a
Document Type: srp
Title: STANDBY LIQUID CONTROL SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070680186.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.5
CFR Part: 
CFR Title: 

Content:
ns have been made that permit appropriate inservice inspection and functional testing of the system. It will be acceptable if the SAR information delineates a testing and inspection program and if the system drawings show the connections and special piping and equipment required by this program. For new applications, the reviewer evaluates the SLCS design provisions to test motor-operated valves under design-basis differential pressure and the piping design provisions for full-flow testing (at maximum design flow) of pumps and check valves, as applicable. In accordance with the staff’s position described in SECY 93-087 (Ref. 8), design features should support inservice valve tests under the maximum practicable differential pressure and flow when it is not practicable to achieve design-basis differential pressure during an inservice test. Where it is not practicable to conduct inservice pump testing at design flow and pressure, the NRC permits analysis to extrapolate to design pressure. C. Using the results of the evaluation performed under SRP Section 4.3, the reviewer determines that the system has the capability to store the required quantity of neutron absorber in solution and that the injection rate is sufficient to bring the reactor from rated power to cold shutdown at any time in core life with the control rods remaining withdrawn in the rated power pattern, taking into account the reactivity gains from complete decay of the rated power xenon inventory, an allowance for imperfect mixing and leakage, and dilution by the residual heat removal system. D. To verify compliance with relevant ATWS rule requirements, the reviewer determines whether the system has the capability to inject into the RPV a borated water solution at such a flow rate, level of boron concentration, and boron-10 isotope enrichment, accounting for RPV volume, that the resulting reactivity control is at least equivalent to that resulting from injection of 326 Lpm (86 gpm) of 13-weight-percent