design characteristics and classification issue of the i&c...

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


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


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)


□ 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)

5


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

6


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

7


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

8


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


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 SSR 1 down position

3 SSR 2 down position

Core Cooling

2 EWSS pool level

2 Pool water temperature



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

9


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)

10


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

11


□ 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

12


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

13


Automatic Seismic Trip System (2)


▶ 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


▶Seismic category : I

14


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

15



▶ No safety functions (No credit in safety analysis)

▶ Comparison & Korean practice

Classification

▶Safety Class

NNS from Korean (USNRC) regulation

Safety Related from IAEA


▶Seismic category : II (Operator security)

Information Processing System (2)

16


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>

17




▶ Korean practice

Classification

▶ Safety Class


Safety Related from IAEA

▶Quality class : T (Reinforcing QA activities required)

▶Seismic category : II (Operator security)

Operator WorkStation (2)

18


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

19


Radiation Monitoring System (2)



▶ All the safety related radiation channels (RGMS, PNMS, PRMS, PGMS) are

classified to safety class as the RPS trip parameters

Classification

▶ Safety Class


Item not important to safety from IAEA

▶Quality class : S ※ The effluent monitoring channels are the quality class T.

▶Seismic category : Non-Seismic

20


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

21

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