SSC s Improvements at IRR1 N. Hazenshprung, T. Makmal, L. - - PowerPoint PPT Presentation

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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


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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

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Content

  • IRR1 overview
  • Ageing Management
  • Management System, maintenance and periodic testing
  • Inspection and peer review
  • Lessons learned from the Fukushima Daiichi Accident
  • Implementation
  • Flow regulating system
  • Control room renovation
  • Replacement of servo-power regulating unit
  • Upgrading the Rabbit’s (pneumatic conveyer) control system
  • Upgrading the confinement isolation mechanism
  • Conclusions
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Israeli Research Reactor-1

  • First criticality: July, 1960
  • Reactor type: MTR, HEU (93%), Swimming Pool type
  • Power: 5 MW
  • Moderator + Coolant : H2O
  • Utilization: Industrial neutron radiography; Neutron diffraction;

Activation analysis; Nuclear physics and health physics research; Students educating , public education and awareness.

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Ageing Management

Management system Maintenance and periodic testing Inspections and peer reviews Lessons learned from Fukushima Daiichi accident

  • Safety infrastructure upgrades
  • System and component improvements
  • Revision of procedures

“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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Management system (RMCP-Reactor Management Computerize Tool)

  • Monitoring staff training, authorizations, enrichment activities etc.
  • Special equipment monitoring: calibration of measurement equipment and

equipment status.

  • Quality assurance (management system) of documentation (procedures,

drawings etc.).

  • Maintenance management and equipment data base.
  • Analyzing database and help in planning future actions.

Maintenance Logbook Personnel safety Water analyzing Data management Logistics

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RMCP maintenance module examples

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%

  • Annual preventive maintenance reminders
  • Equipment database
  • Statistics

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

Maintenance and periodic testing

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Ageing Management

Management system Maintenance and periodic testing Inspections and peer reviews Lessons learned from Fukushima Daiichi accident

  • Safety infrastructure upgrades
  • Systems and components improvements
  • Revision of procedures

“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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Inspection and peer reviews

IRR1

Safety Division

  • f SNRC

Safety Committee Nuclear Regulatory Body Domestic peer reviews

IAEA INSARR

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

  • Safety infrastructure upgrades
  • Systems and components improvements
  • Revision of procedures

“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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Lessons learned from Fukushima Daiichi accident

Fukushima accident has catalyzed interface-procedures in reactor licensing

  • process. Major benefit to aging-management is an agreed-upon action-plan,

involving both the regulator and the facility, based on IAEA SRS-80:

  • Complementary operational procedures.
  • Installation of accelerometer for triggering automatic shutdown.
  • Dynamic analysis of key systems.
  • Upgrade of Electrical and Water-Supply system.

* Int. Conf. on RR Safe Management and Effective Utilization, Vienna, Nov. 2015.

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Implementation - Example #1 Renewal of flow regulating system (1/3)

  • Several 10" butterfly valves regulate the flow rate of the primary

cooling system (installed 40 years ago).

  • Degradation (difficulties in operation, leaks) and obsolescence (lack of

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:

  • Fail Safe actuator (normally closed).
  • Electro-pneumatic control instead of full pneumatics.
  • Electronic and electro-mechanic component – approved according

IEC-61508 with SIL 2/3.

  • No change in valve location nor valve size.

Principle of operation

Renewal of flow regulating system (2/3)

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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  • ff-line commission testing

Characterization and plan Present to the safety committee Off -line test Work permit granted Installation On-line test Final approval and report

Renewal of flow regulating system (3/3)

Valves system: Installation and commissioning

  • ld system (right) vs new (left)
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control room view- 2007

  • Control console
  • Chart recorders
  • New fire detection and extinguishing system
  • Upgrade the UPS units
  • Data acquisition (DAQ) and HMI systems

control room view- 2017

Implementation – Example #2 Control Room Renovation

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PID controller

WRM

DAQ galvanic isolator

CIC demand Chart recorder

M

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)

Implementation - Example #3 Replacement of servo power regulating unit (1/4)

M

Regulating rod drive

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PID controller

WRM

DAQ galvanic isolator

CIC demand Chart recorder

M

low current voltage

Replacement of servo power regulating unit (2/4)

M

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PID controller WRM DAQ galvanic isolator CIC low current voltage demand

Replacement of servo power regulating unit (3/4)

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New “servo” unit – commissioning tests

Stabilization time and overshoot – step power demand response Steady-state example

Replacement of servo power regulating unit (4/4)

  • ld servo unit

new “servo" unit new

  • ld
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  • Obsolescence of the system
  • Malfunctions of the electronic

and electro-mechanic devices

  • Controlled by PLC
  • Advanced safety features
  • Standard components

Implementation - Example #4 Upgrading the Rabbit’s Control System

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The old mechanism: an electromagnet with a mechanical latch The new concept is based only on the electromagnetic coupling

  • “Fail safe“ design.
  • “Off the shelf" products, which are used in safety systems for fire

protection doors (UL listed).

Material strength calculations design special adapters "mock-up" commissioning tests

Implementation - Example #5 upgrading the confinement isolation mechanism

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Conclusions

  • In

recent years, IRR1 underwent major upgrades and improvements as part of an ageing management program.

  • Obsolete SSC’s are updated by modern state-of-the-art solutions.
  • Existing programs and lessons learned from special occasions

were integrated into the ageing management program.

  • We will be happy to share our experience and knowledge with
  • ther RR groups.
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Thank You!