Standby Liquid Control
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Is used to inject boron into reactor water to lower reactivity.
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System
Automatic Depressurization System
Auxiliary Building Gas Treatment System
Auxiliary Feedwater
Circulating Water System
Containment Spray
Control Rod
Control Room Emergency Air Temperature Control System
Control Room Emergency Filtration System
Control Room Emergency Ventilation
Control Room Emergency Ventilation Air Supply
Control Room Envelope
Core Spray
Core Standby Cooling System
Cresent Area Ventilation and Cooling
Critical Function Monitoring System
Decay Heat Removal
Drywell Continuous Atmospheric Monitor
Electrohydraulic Control
Emergency Cooling Tower
Emergency Core Cooling System
Emergency Diesel Generator
Emergency Equipment Cooling Water
Emergency Feedwater Actuation System
Emergency Feedwater Initiation and Control
Emergency Feedwater System
Emergency Gas Treatment System
Emergency Response Data System
Extraction steam
Feedwater
Fuel Pool Cooling and Cleanup
HVAC
High Pressure Coolant Injection
High Pressure Core Spray
Intermediate Range Monitor
Low Pressure Coolant Injection
Low Pressure Cooling Injection
Main Condenser
Main Steam
Main Steam Isolation Valve
Main Steam Line
Main Steam Safety Valve
Main Transformer
Main Turbine
Main Turbine Bypass System
Mechanical Pressure Regulator
Moisture Separator Reheater
Permanent Magnet Generator
Post Accident Monitoring
Primary Containment Isolation System
Primary containment
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[Findings]
Site
Start date
Title
Description
IR 05000354/2025003
Hope Creek
17 December 2025
Integrated Inspection Report 05000354/2025003
IR 05000324/2025003
Brunswick
4 December 2025
Integrated Inspection Report 05000324/2025003 and 05000325/2025003
IR 05000458/2025013
River Bend
3 December 2025
Age-Related Degradation Inspection Report 05000458/2025013
ML25317A711
Peach Bottom
13 November 2025
Introduction of Lead Use Assemblies
CNL-25-103, Request for Exemptions from 10 CFR 50.55(a)(3)(iii) and 10 CFR 50.55a(y) for Adoption of Code Case OMN-31
Browns Ferry
16 October 2025
Request for Exemptions from 10 CFR 50.55(a)(3)(iii) and 10 CFR 50.55a(y) for Adoption of Code Case OMN-31
ML25287A025
Browns Ferry
14 October 2025
Alternative Request BFN-IST-06
ML25273A236
30 September 2025
Draft Appendix a to LIC-112, Power Uprate Process Graded Approach for Determining Power Uprate Level of Review
L-MT-25-031, Site Specific Emergency Action Level Technical Basis Documents Change
Monticello
24 September 2025
Site Specific Emergency Action Level Technical Basis Documents Change
ML25266A128
Browns Ferry
22 September 2025
Acceptance Review Results for Browns Ferry Nuclear Plant, Unit 3, Request for Alternative BFN-IST-06 Re Group B Quarterly Pump Test
CNL-25-108, American Society of Mechanical Engineers Operation and Maintenance Code Request for Alternative BFN-IST-06
Browns Ferry
18 September 2025
American Society of Mechanical Engineers Operation and Maintenance Code Request for Alternative BFN-IST-06
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