design characteristics and classification issue of the i&c...
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1 KAERI
TRTR 2013 Annual Conference, September 23-26, St. Louis, MO
Design Characteristics and
Classification Issue of the I&C
Systems for the JRTR
J. Y. Keum*, J. Y. Park*, H.S. Kim**, and Y. K. Kim*
* Republic of Korea, Korea Atomic Energy Research Institute ** Republic of Korea, Chungnam National Univ.
Jordan Research & Training Reactor
Contents
- Overview of JRTR I&C
* Configuration of JRTR I&C Systems
* Main I&C Classification Issue
- Design Features and Classification of
JRTR I&C Systems
- Conclusion
2
Jordan Research & Training Reactor
Configuration of JRTR I&C System
3
SCR
Instrument Room
HP Room
MCR
RRS PICS
A
PICS
B
ASTS
MCR
HVAC
LDP Controller
VDU/Soft
Controllers
CAR/SSR Circuit Breaker
NMS(N)/PNMS(N)/PI(N)
Sensors/Pumps/Valves
PCS/SCS/HWS
PWMS/EWSS/HTWS
Liquid/Solid RS
Service Water System
Compressed Air System
Electrical System
NAAF System
RPS-A RPS-B RPS-C
PAMS-B PAMS-A
2/3 Voting
BP
2/3 Voting
BP
2/3 Voting
BP
Integrated Monitoring & Control Network (Non-Safety)
NMS/PNMS/RGMS/PRMS/PGMS
/PI(S)
APS-A APS-B
CAR
Stepping
Motor
RMS
Accelerometers
Free Field
Mat –
Foundation
Pool Top
CR or Roof
Gamma Area Monitor
Liquid Monitor
Gaseous Effluent Monitor
Stack Monitor
Particle / Iodine/ Noble Gas
/ Tritum Monitor
Safety Network
VDU
Controller
Manual Trip
CAR/SSR
Contactor
Manual Trip
Safety Information Network
Non-Safety Network
Hardwired Connection
Safety Data Flow
Non-Safety Information Flow
Manual Trip
Safety
System
NMS/
PI(S)
IPS
RASS
3
Jordan Research & Training Reactor
Main I&C Classification Issue (1)
□ Design Basis for I&C Safety Classification
IAEA Safety Standards No. NS-R-4, “Safety of Research Reactor”, 2005.
ANSI/ANS 51.1(1983) – Nuclear safety criteria for the design of stationary pressurized water plants
2012-09 MEST Notice, Korea
MEST (Ministry of Education, Science and Technology)
Jordan Research & Training Reactor
□ Items for Quality Class T based on ANSI/ANS 51.1 &
MEST (2012-09) MEST Notice, Korea – Some NNS equipment
has one or more selected, but limited, requirements that are
specified to ensure acceptable performance of specific NNS
functions below
1. Processing of radioactive waste
2. Purification of radioactive material during normal operation
3. Processing of radioactive waste from irradiated neutron absorbers for reuse
4. Monitoring of radioactive effluents -> (RMS)
5. Resisting the failure of SC-1/2/3 equipment’s safety functions
.
.
.
12. Protecting SC-2/3 equipment for safe shutdown following fire
13. Monitoring of Variables :
- plant operating conditions on technical specification limits -> (PICS & IPS)
- status of protection system bypasses -> (IPS-BISI)
- status of SC-1/2/3 equipment -> (IPS from RPS & PAMS)
- aid in determining the cause or consequences of events for post accident
investigation -> (IPS – Type D of PAMS)
Main I&C Classification Issue (2)
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Jordan Research & Training Reactor
Reactor Protection System
TR TR
CH-A
BISTABLE
PROCESSOR
A B C
CH-A
COINCIDENCE
LOGIC
A B C
CH-A
INITIATION
LOGIC
A B C
CRDM TRIP
ACTUATION
LOGIC
CRDM
TRIP
SSDM
TRIP
CH-B
BISTABLE
PROCESSOR
A B C
CH-B
COINCIDENCE
LOGIC
A B C
CH-B
INITIATION
LOGIC
CH-C
BISTABLE
PROCESSOR
A B C
CH-C
COINCIDENCE
LOGIC
A B C
CH-C
INITIATION
LOGIC
A B C
SB
ACTUATION
LOGIC
A B C
CID
ACTUATION
LOGIC
SB
ACTUAT
ION
CID
ACTUATIO
N
TR-SENSOR
AND TRANSMITTER
BISTABLE
FUNCTION
TRIP & EACH ESF
FUNCTION, PER
CHANNEL
(Digital-based)
GENERAL
COINCIDENCE
LOGIC TRIP &
EACH ESF
FUNCTION, PER
CHANNEL
(Analog-based)
INITIATION
LOGIC TRIP &
EACH ESF
FUNCTION, PER
CHANNEL
ACTUATION
LOGIC FOR EACH
TRIP, SB,
CI FUNCTION
TRIP FUNCTION
TR TR TR TR
CH-A
MAINT. &
TEST
PROCESSOR
CH-A
IF.& TEST
PROCESSOR
CH-B
MAINT. &
TEST
PROCESSOR
CH-B
IF.& TEST
PROCESSOR
CH-C
MAINT. &
TEST
PROCESSOR
CH-C
IF.& TEST
PROCESSOR
CHANNEL A CHANNEL B CHANNEL C
NOTE:HARDWIRED CABLE
INTERNAL NETWORK
A B C
SSDM TRIP
ACTUATION
LOGIC
ESF FUNCTION
□ Design Features
- 3 Redundant Channels
- Hybrid of Digital and Analog
- Provisions of Manual
Initiation
- ESF Actuation
□ Classification
- Safety Class: 3
- Seismic Category: I
- Quality Class: Q
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Jordan Research & Training Reactor
Alternate Protection System (1)
APS
CH A
BISTABLE
CONTROLLER
APS
CH B
BISTABLE
CONTROLLER
TR TRTR-SENSOR
AND
TRANSMITTER
CHANNEL A
TR TR
CHANNEL A
MANUAL
TRIP
MANUAL
TRIP
120VAC 120VAC
RPS
ACTUATION
CIRCUIT
ACTUATION
CIRCUIT
RPS
+
-
+
-
CRDM
#1
CRDM
#2
CRDM
#3
CRDM
#4
SSDM
#1
SSDM
#2
INITIATION
CIRCUIT
INITIATION
CIRCUIT
□ Design Features
- Diverse protection against a CCF
of RPS
- Two Redundant Channels with 2-out-2 Coincidence Logic
- Physical separation and electrical isolation from the RPS
- Manual initiation
- APS trip parameters to be selected by DID & Diversity (D3) analysis
- No credit in safety analysis
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Jordan Research & Training Reactor
Alternate Protection System (2)
Bases on Classification
▶Diverse mean to act against the software CCF of RPS, which is beyond design
basis accident (Not for DBA)
▶USNRC-0800 (SRP) allows it non-safety feature but a special QA requirements
as per NRC Generic Letter 85-06 under 10CFR 50.62.
▶Korean (US-based) practice on the non-safety ATWS to NPPs
▶A safety-grade second protection system need not a mandatory but an option
depending on the characteristics of research reactor.
Classification
▶Safety Class
NNS from Korean (US) regulation
Item important to safety (safety related) from IAEA
▶Quality class : T
▶Seismic category : Non-Seismic
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Jordan Research & Training Reactor
Post Accident Monitoring System (1)
Type Subgroup Category PAMS Variables
Type A Plant Specific - N/A
Type B
Reactivity Control 1 Ex-core neutron
Core Cooling
1 PCS flow
1 Core differential pressure
1 Reactor outlet temperature
1 PAMS pool level
1 Flap valve 1 position
1 Flap valve 2 position
Confinement
Integrity 1 Confinement isolation damper position
Type C
Fuel Cladding 1 Pool surface radiation
PCS Boundary
Integrity 1 PCS neutron (FFDS)
Type D
Reactivity Control
3 CAR 1 down position
3 CAR 2 down position
3 CAR 3 down position
3 CAR 4 down position
3 SSR 1 down position
3 SSR 2 down position
Core Cooling
2 EWSS pool level
2 Pool water temperature
3 Flap valve 1 position
3 Flap valve 2 position
Auxiliary/Emergen
cy Water Supply
System
2 EWSS flow
2 EWSS injection valve position
3 DWST water level
3 Service pool water level
3 Service pool water temp.
RCI Ventilation 2 RCI ventilation recirculation mode
Power Supplies
2 EPS status
3 EPS oil status
2 UPS status
Type E
Area Radiation 2 Reactor hall gamma activity
Airborne
Radioactive
Materials
Released from
Plant
2 Stack particulate activity
2 Stack iodine activity
2 Stack noble gases activity
“10 Safety Parameters”
“23 Non-safety Parameters”
□ Design Features
- 2 Redundant
Channels
- Digital computers
- Critical analog
displays in SCR
□ Classification
- Safety Class: 3
- Seismic Category: I
- Quality Class: Q
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Jordan Research & Training Reactor
Post Accident Monitoring System (2)
PAMS Channel B Cabinet PAMS Channel A Cabinet
19” Flat Panel Display PC (Display of Category 1 Train A Parameters)
19” Flat Panel Display PC (Display of Category 1
Train B Parameters)
PAMS Processor Module A PAMS Processor Module B
Category 1 Signals to IPS
Isol. Isol.
OWS PAMS displays at the MCR
IPS
Non-safety Signals (29 parameters)
Signal Input Module
Safety Signals A (10 parameters)
Communication Link Module
Train A Instruments RPS ITP-A
Signal Input Module
Communication Link Module
Train B Instruments RPS ITP-B
Data Storage Device
Data Storage Device
HDSR
Safety Signals B (10 parameters)
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Jordan Research & Training Reactor
Reactor Regulating System
□ Design Features :
- Dual redundant system
- Reactor power control using a closed loop
feedback control algorithm
- Stepping motor mechanism
□ Classifications : - Safety Class : Non-nuclear safety
- Seismic Category : Non
- Quality Class : T
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Jordan Research & Training Reactor
□ Design Features :
- Dual Redundant digital computer system
- Control of process systems’ equipment
(pumps, valves, fans, heaters and etc.)
- Continuous monitoring of process
- Data and Alarm processing
- No credit in safety analysis
□ Classification :
- Safety Class
Non Nuclear Safety from Korean
regulation
Item important to safety (safety related)
from IAEA
- Seismic Category : Non Seismic
- Quality Class : T
Process Instrumentation & Control system
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Jordan Research & Training Reactor
Automatic Seismic Trip System (1)
□ Design Features
- Reactor trip if the earthquake motion exceeds the level of OBE at the site.
- Monitoring and analysis of the seismic motion of the site in a continuous basis.
- Major components of ASTS
◦ Five (5) tri-axial accelerometers
◦ One (1) seismic switch for OBE
◦ One (1) ASTS cabinets
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Jordan Research & Training Reactor
Automatic Seismic Trip System (2)
Bases on Classification
▶ Earthquake is classified to a special event (not a DBA), which is not required
safety SSCs in the Korea regulations.
▶ ASTS component considered to be at mild conditions during the earthquake
☞ No need to apply the EQ requirements for safety system but enough with
seismic qualification
▶USNRC RG1.12 & ANS 2.2 considered enough as the SMS(Seismic Monitoring
System for power plant. ( No requirement of shutdown at earthquake)
▶Korean (US-based) practice on the non-safety ASTS to NPPs
Classification
▶Safety Class
NNS from Korean (US) regulation
Item important to safety (safety related) from IAEA
▶Quality class : T
▶Seismic category : I
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Jordan Research & Training Reactor
Information Processing System (1)
□ Design Features
- Plant information processing
(collecting, recording, retrieval)
- Alarm processing
- Providing key process variables
to ERFs
- Redundant architecture for high
availability
- Isolation from safety systems
Control Level
Field Level
Information Level
(IPS Coverage)
Operation Level
Interfacing Layer between
Operation and Control
Historical & Centralized
Database Management System
Network Control, Monitoring
and Management
Large DisplayOWSOWS OWS
Large Display
Redundant Monitoring & Control Networks
MCR SCR
Protection
Status
Regulating
Status
Process
Instruments
Status
Radiation,
Seismic,
HVAC Status
Integrated Information Provision
to MCR/SCR
RR-wide Status Monitoring
Redundant IPS Servers
Network Controller
Engineering Computer
Network Control
Reactor Information Management
RR Centralized
DBMS
In/Out Processing
Logics
Alarm Processing
Logics
Process Variable Monitoring Logics
Reactor Information Management
RR Centralized
DBMS
In/Out Processing
Logics
Alarm Processing
Logics
Process Variable Monitoring Logics
Network Controller
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Jordan Research & Training Reactor
Bases on Classification
▶ No safety functions (No credit in safety analysis)
▶ Comparison & Korean practice
Classification
▶Safety Class
NNS from Korean (USNRC) regulation
Safety Related from IAEA
▶Quality class : T
▶Seismic category : II (Operator security)
Information Processing System (2)
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Jordan Research & Training Reactor
Operator WorkStation (1)
Functions
– To display monitoring
information received from
IPS
– To display control
interfaces for control
commands to be sent to
RRS and PICS
Interfacing Systems via
non-safety networks
– IPS: monitoring
information
– PICS: control commands
– RRS: control commands
< Data flow diagram >
< Interfacing systems via networks>
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Jordan Research & Training Reactor
Bases on Classification
▶ No safety functions (No credit in safety analysis)
▶ Korean practice
Classification
▶ Safety Class
NNS from Korean (USNRC) regulation
Safety Related from IAEA
▶Quality class : T (Reinforcing QA activities required)
▶Seismic category : II (Operator security)
Operator WorkStation (2)
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Jordan Research & Training Reactor
Radiation Monitoring System (1)
GAMMA AREA
MONITOR
PARTICLE MONITOR
IODINE MONITOR
GAS EFFLUENT MONITOR
STACK MONITOR
RMS
IPS
RMS
Computer
Operator
Workstation
FIELD
INSTRUMENT
ROOM MAIN CONTROL ROOM
HEALTH & PHYSICS ROOM
□ Design Features
- Measuring, indicating and
alarming radiation level to
H/P room and MCR
- Data Acquisition
- Functions of monitors
◦ Gamma Area monitoring
◦ Gas effluent monitoring
◦ Stack monitoring
◦ Iodine monitoring
◦ Particle monitoring
- Safety-related monitors
designated to RPS
- Independent network
- Local alarms
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Jordan Research & Training Reactor
Radiation Monitoring System (2)
Bases on Classification
▶ No safety functions (No credit in safety analysis)
▶ All the safety related radiation channels (RGMS, PNMS, PRMS, PGMS) are
classified to safety class as the RPS trip parameters
Classification
▶ Safety Class
NNS from Korean (USNRC) regulation
Item not important to safety from IAEA
▶Quality class : S ※ The effluent monitoring channels are the quality class T.
▶Seismic category : Non-Seismic
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Jordan Research & Training Reactor
System Safety Class Seismic
Category S/W Class
Quality
Class Remark
USNRC IAEA
RPS SC-3 Safety system I SC Q
PAMS SC-3 Safety system I SC Q
RRS Non-Safety Safety related Non NS T
APS Non-Safety Safety related Non ITS T
IPS Non-Safety Safety related Non NS S->T Quality
Upgrade
ASTS Non-Safety Safety related I ITS T
PICS Non-Safety Safety related Non NS S->T Quality
Upgrade
RMS - Area Monitor Non-Safety Non NS S
RMS – Effluent
Monitor Non-safety Safety related Non NS S->T
Quality
Upgrade
OWS Non-Safety Safety related II NS S->T Quality
Upgrade
LDP Non-Safety II NS S
Concluding Remarks
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