1 IGORR 2017
Ageing Management and SSC’s Improvements at IRR1
- N. Hazenshprung, T. Makmal, L. Zilberfarb,
- K. Ben-meir, S. Alony, M. Bisiakov
SNRC Israel
SSC s Improvements at IRR1 N. Hazenshprung, T. Makmal, L. - - PowerPoint PPT Presentation
Ageing Management and SSC s Improvements at IRR1 N. Hazenshprung, T. Makmal, L. Zilberfarb, K. Ben-meir, S. Alony, M. Bisiakov SNRC Israel 1 IGORR 2017 Content IRR1 overview Ageing Management Management System, maintenance
1 IGORR 2017
SNRC Israel
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Ageing Management
Management system Maintenance and periodic testing Inspections and peer reviews Lessons learned from Fukushima Daiichi accident
“In practice, the ageing management program at a research reactor is accomplished by coordinating existing programs, including maintenance, periodic testing and inspection programs” [IAEA SSG-10]
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equipment status.
drawings etc.).
Maintenance Logbook Personnel safety Water analyzing Data management Logistics
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Compresed air 7% Generators 7% Water pipes and valves 4% Demineralization systems 14% Electrical disterbution 7% Cooling Towers 11% HVAC 14% Forklifts and Cranes 14% Blowers 4% Pumps 7% low voltage 7% Irradiation instrumantations 4%
corrective maintenance by system
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Operational status Maintenance Periodic testing Routine Non-Routine Corrective maintenance System Upgrade System Replacement Monthly Quarterly Annually (per sys) Pre-operational Monthly check-up Quarterly check-up Semi-annual check-up Annual check-up Maintenance supervisor Operation engineer
Reactor manager’s approval
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Ageing Management
Management system Maintenance and periodic testing Inspections and peer reviews Lessons learned from Fukushima Daiichi accident
“In practice, the ageing management program at a research reactor is accomplished by coordinating existing programs, including maintenance, periodic testing and inspection programs” [IAEA SSG-10]
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Safety Division
Safety Committee Nuclear Regulatory Body Domestic peer reviews
quarterly Twice a year ~once every two years National
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Ageing Management
Management system Maintenance and periodic testing Inspections and peer reviews Lessons learned from Fukushima Daiichi accident
“In practice, the ageing management program at a research reactor is accomplished by coordinating existing programs, including maintenance, periodic testing and inspection programs” [IAEA SSG-10]
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Fukushima accident has catalyzed interface-procedures in reactor licensing
involving both the regulator and the facility, based on IAEA SRS-80:
* Int. Conf. on RR Safe Management and Effective Utilization, Vienna, Nov. 2015.
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cooling system (installed 40 years ago).
spare parts) necessitated renewal of this safety related system.
Old diaphragm actuator Old butterfly valve
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The new system is based on:
IEC-61508 with SIL 2/3.
Principle of operation
HMI
current supply by controller
Positioner Actuator Valve
feedback
feedback
main Relief valve 4…20 mA regulated air high Air Pressure emergency pressure relief valve integrated pressure relief valve
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Characterization and plan Present to the safety committee Off -line test Work permit granted Installation On-line test Final approval and report
Valves system: Installation and commissioning
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control room view- 2007
control room view- 2017
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PID controller
WRM
DAQ galvanic isolator
CIC demand Chart recorder
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low current voltage
Servo unit objective: to convert the output of the Wide Range Monitor (voltage) to the input of the regulating rod controller (resistance)
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Regulating rod drive
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PID controller
WRM
DAQ galvanic isolator
CIC demand Chart recorder
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low current voltage
M
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PID controller WRM DAQ galvanic isolator CIC low current voltage demand
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Stabilization time and overshoot – step power demand response Steady-state example
new “servo" unit new
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and electro-mechanic devices
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The old mechanism: an electromagnet with a mechanical latch The new concept is based only on the electromagnetic coupling
protection doors (UL listed).
Material strength calculations design special adapters "mock-up" commissioning tests
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