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1
The Opal Reactor’s I&C
Systems
Charles R Morris
Ex Group Leader Instrumentation and
Control OPAL Engineering
From a January 12 2007 IAEA
Presentation
2
Topics
 OPAL General Information
 Instrumentation Interconnection
 Reactor Protection Systems
 Post Accident Monitoring System
 Reactor Control and Monitoring System
 Human Machine Interface
 Radiation Monitoring
3
The OPAL Facility
4
OPAL Reactor General
Information
 OPAL stands for Open Pool Australian
Lightwater reactor. Designed by INVAP
Argentina
 20 MWth core power, which correlates to a
flux of 1014 neutrons per cm2 per second
 Compact core (approx 450mm cubed)
compatible with non pressurized cooling
system
 Upwards forced cooling of reactor core, no
pumps needed for core cooling once
shutdown
 D2O reflector with intermediate cooling
system
 35 Day Operating Cycle with 2 Day Refueling
5
6
Reactor Pool
7
Instrumentation Interconnection
Main Control
Room
Emergency Control
Centre
Reactor Control and
Monitoring System (RCMS)
Cat 2
Post Accident Monitoring
System (PAM) Cat 1
First Reactor Protection
System (FRPS) Cat 1
Second Reactor
Protection
System (SRPS)
Cat 1
First Shutdown System
(FSS) Cat 1
Second Shutdown
System (SSS)
Cat 1
I
I
I
I I
Digital
Hard-wired
Cat 1 Isolation Device
I
I
8
Reactor Protection Systems
FRPS and SRPS Nucleonics
9
OPAL Reactor Protection
Systems
 First Reactor Protection
System, Digital
– Triplicated Triconex Systems
 Functions
– Fast Insertion of Control Rods
– Reactor Start Up
– Containment Energy Removal
– Reactor Containment Isolation
10
FRPS Interconnection
Reactor
Trip
Tricon Train 1
Tricon Train 2
Tricon Train 3
Final Actuation
Logic Relays
Nucleonics Train 1
Nucleonics Train 2
Nucleonics Train 3
Flow
Temp
Pressure
Position
Seismic
Radiation
Power
Availability
Triconex
sampling rate too
slow to satisfy
nucleonic trip
requirements
11
Second Reactor Protection
System Description
 Analogue system
 Foxboro Spec 200
– Analogue Technology
– Certified Class 1E (nuclear)
applications.
– Operating in over 100
Nuclear Power Plants with
over 1,000,000 modules in
operation
12
SRPS
Interconnection
SPEC 200 Train 1
SPEC 200 Train 2
SPEC 200 Train 3
Final Actuation
Logic Relays
Nucleonics
Temp
∆ Temp
∆ Pressure
Seismic
Level
FSS Failure
Reactor Trip
13
Second Reactor Protection
System Function
 Partial draining of
the Reflector Vessel
14
Post Accident Monitoring
 Duplicated System for redundancy
 No Control features other then video and
audio
 Duplicated displays in the MCR and ECC
 Spec 200 analogue system
15
Reactor Control &
Monitoring System
 Foxboro I/A Series,
Distributed Control
System
 Interface to First and
Second Reactor
Protection Systems
through read only
communication
16
NBEX
+13
+0
-5
NBEX
NODEBUS
CP101 CP102 CP103 CP104 CP105 CP106
NODEBUS
AUX. BDG SUBSTATION
REACTOR
NBEX
NBEX
AW51D
CBLIFT NBEX
NODEBUS
FCMS
AW51E
Main Console
CBLIFT
NODEBUS
RCMS
FU
901
FU
902
FU
601
FU
702
FU
705
FU
704
FU
706
FU
708
FU
710
COOLING TWR
+10
SRPS
PAM
FU
711
AW51D
PTS
Irradiation
Facility
Radioprot.
Reactor
Mngr
Shift
Supervisor
Health
Physics
NTD
FoxGuard
FRPS
(Tricon)
Neutron
Beam
NAA
Rack
mounted
Desktop
Pedestal/Wall
Panel
Facilities
RCMS-FCMS Architecture
Level
NBEX
FU
507
FU
404
FU
502
FU
401
FU
004
FU
006
FU
003
FU
008
FU
009
FU
005
FU
007
FU
001
FU
103
FU
105
FU
703
CNS
HUB HUB
HUB
HUB
Radioprot.
Emergency
Console
Local Supervision Units (Ethernet)
SU-501 SU-502 SU-503 SU-504 SU-505 SU-506
SU-507
SU-508
SU-101 SU-102
SU-204
SU-201 SU-202 SU-203
SU-001 SU-002 SU-003
SU-601 SU-701
SU-103
SU-301
SU-510 SU-511
SU-509
SU-104
SU-514
SU-513
Nucleonic
Channels
RMS
CP107
CP108 CP109 CP110
Irradiation Facility
CNS-PS
NBF &
CNS
FU
504
FU
403
FU
101
FU
505
FU
102
FU
506
FU
503
FU
402
FU
010
17
Reactor Control & Monitoring
System
 Foxboro I/A Series DCS with two
separate functions, RCMS and FCMS
 Foxboro Proprietary Communication links to the
three Triconex safety trains
 Modbus communication with:
– Cold Neutron Source, Eurotherm controller
– Radiation Monitoring, INVAP µprocessors
– Rod Control, Siemens PLC
– Building HVAC system
– Fire Protection System
– Diesel Generators
18
Primary Cooling RCMS
Display
19
Typical Trip Logic RCMS Display
20
Human Machine Interface
Operator Consoles
– Visual Display Units driven by the RCMS
– Hardwired control and indication panels
 Protection Systems Parameters
 Control Rods
PAM Panel
 PA System, video control, trending
Dedicated function visual display units
 Alarm manager
 Radiation Monitoring, Electrical, Irradiation Facilities
21
Main Control Room
22
Emergency Control Centre
23
Safety WallPanels
24
Radiation Monitors
 Monitoring of Liquids
 Liquid Effluent Monitors
 Failed Fuel and Rig Monitors
 Liquid Systems Monitors
 Monitoring of Gases
 Air Effluent Monitors
 Tritium Monitors
 Area Monitoring (Personnel Protection)
 Area Radiation Monitors
 Neutron Dose Rate Monitors
 Monitoring of Personnel
 Walk Through Contamination Monitors
 Wall Mounted Friskers
25
Radiation Monitors
Secondary Water
Stack Area
Personnel
Liquid Waste
Fuel
26
20Mw Cherenkov Effect

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Opal Systems I&C.pdf

  • 1. 1 The Opal Reactor’s I&C Systems Charles R Morris Ex Group Leader Instrumentation and Control OPAL Engineering From a January 12 2007 IAEA Presentation
  • 2. 2 Topics  OPAL General Information  Instrumentation Interconnection  Reactor Protection Systems  Post Accident Monitoring System  Reactor Control and Monitoring System  Human Machine Interface  Radiation Monitoring
  • 4. 4 OPAL Reactor General Information  OPAL stands for Open Pool Australian Lightwater reactor. Designed by INVAP Argentina  20 MWth core power, which correlates to a flux of 1014 neutrons per cm2 per second  Compact core (approx 450mm cubed) compatible with non pressurized cooling system  Upwards forced cooling of reactor core, no pumps needed for core cooling once shutdown  D2O reflector with intermediate cooling system  35 Day Operating Cycle with 2 Day Refueling
  • 5. 5
  • 7. 7 Instrumentation Interconnection Main Control Room Emergency Control Centre Reactor Control and Monitoring System (RCMS) Cat 2 Post Accident Monitoring System (PAM) Cat 1 First Reactor Protection System (FRPS) Cat 1 Second Reactor Protection System (SRPS) Cat 1 First Shutdown System (FSS) Cat 1 Second Shutdown System (SSS) Cat 1 I I I I I Digital Hard-wired Cat 1 Isolation Device I I
  • 8. 8 Reactor Protection Systems FRPS and SRPS Nucleonics
  • 9. 9 OPAL Reactor Protection Systems  First Reactor Protection System, Digital – Triplicated Triconex Systems  Functions – Fast Insertion of Control Rods – Reactor Start Up – Containment Energy Removal – Reactor Containment Isolation
  • 10. 10 FRPS Interconnection Reactor Trip Tricon Train 1 Tricon Train 2 Tricon Train 3 Final Actuation Logic Relays Nucleonics Train 1 Nucleonics Train 2 Nucleonics Train 3 Flow Temp Pressure Position Seismic Radiation Power Availability Triconex sampling rate too slow to satisfy nucleonic trip requirements
  • 11. 11 Second Reactor Protection System Description  Analogue system  Foxboro Spec 200 – Analogue Technology – Certified Class 1E (nuclear) applications. – Operating in over 100 Nuclear Power Plants with over 1,000,000 modules in operation
  • 12. 12 SRPS Interconnection SPEC 200 Train 1 SPEC 200 Train 2 SPEC 200 Train 3 Final Actuation Logic Relays Nucleonics Temp ∆ Temp ∆ Pressure Seismic Level FSS Failure Reactor Trip
  • 13. 13 Second Reactor Protection System Function  Partial draining of the Reflector Vessel
  • 14. 14 Post Accident Monitoring  Duplicated System for redundancy  No Control features other then video and audio  Duplicated displays in the MCR and ECC  Spec 200 analogue system
  • 15. 15 Reactor Control & Monitoring System  Foxboro I/A Series, Distributed Control System  Interface to First and Second Reactor Protection Systems through read only communication
  • 16. 16 NBEX +13 +0 -5 NBEX NODEBUS CP101 CP102 CP103 CP104 CP105 CP106 NODEBUS AUX. BDG SUBSTATION REACTOR NBEX NBEX AW51D CBLIFT NBEX NODEBUS FCMS AW51E Main Console CBLIFT NODEBUS RCMS FU 901 FU 902 FU 601 FU 702 FU 705 FU 704 FU 706 FU 708 FU 710 COOLING TWR +10 SRPS PAM FU 711 AW51D PTS Irradiation Facility Radioprot. Reactor Mngr Shift Supervisor Health Physics NTD FoxGuard FRPS (Tricon) Neutron Beam NAA Rack mounted Desktop Pedestal/Wall Panel Facilities RCMS-FCMS Architecture Level NBEX FU 507 FU 404 FU 502 FU 401 FU 004 FU 006 FU 003 FU 008 FU 009 FU 005 FU 007 FU 001 FU 103 FU 105 FU 703 CNS HUB HUB HUB HUB Radioprot. Emergency Console Local Supervision Units (Ethernet) SU-501 SU-502 SU-503 SU-504 SU-505 SU-506 SU-507 SU-508 SU-101 SU-102 SU-204 SU-201 SU-202 SU-203 SU-001 SU-002 SU-003 SU-601 SU-701 SU-103 SU-301 SU-510 SU-511 SU-509 SU-104 SU-514 SU-513 Nucleonic Channels RMS CP107 CP108 CP109 CP110 Irradiation Facility CNS-PS NBF & CNS FU 504 FU 403 FU 101 FU 505 FU 102 FU 506 FU 503 FU 402 FU 010
  • 17. 17 Reactor Control & Monitoring System  Foxboro I/A Series DCS with two separate functions, RCMS and FCMS  Foxboro Proprietary Communication links to the three Triconex safety trains  Modbus communication with: – Cold Neutron Source, Eurotherm controller – Radiation Monitoring, INVAP µprocessors – Rod Control, Siemens PLC – Building HVAC system – Fire Protection System – Diesel Generators
  • 19. 19 Typical Trip Logic RCMS Display
  • 20. 20 Human Machine Interface Operator Consoles – Visual Display Units driven by the RCMS – Hardwired control and indication panels  Protection Systems Parameters  Control Rods PAM Panel  PA System, video control, trending Dedicated function visual display units  Alarm manager  Radiation Monitoring, Electrical, Irradiation Facilities
  • 24. 24 Radiation Monitors  Monitoring of Liquids  Liquid Effluent Monitors  Failed Fuel and Rig Monitors  Liquid Systems Monitors  Monitoring of Gases  Air Effluent Monitors  Tritium Monitors  Area Monitoring (Personnel Protection)  Area Radiation Monitors  Neutron Dose Rate Monitors  Monitoring of Personnel  Walk Through Contamination Monitors  Wall Mounted Friskers
  • 25. 25 Radiation Monitors Secondary Water Stack Area Personnel Liquid Waste Fuel