ML20116L467

Forwards Presentation Matl from Advanced Reactor Programs Advanced BWR Control Room Design Presented by Ma Ross in Tokyo,Japan on 920403-04

ML20116L467
Person / Time
Site:	05200001
Issue date:	09/16/1992
From:	Fox J GENERAL ELECTRIC CO.
To:	NRC
References
NUDOCS 9211180320
Download: ML20116L467 (66)

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GENuclearEnergy AdvancedReactorProgranis ABWR ControlRoom Design Presentedto USNRC M. A. Ross April 3-4,1992 Tokyo, Japan

u DISCUSSION TOPICS Mackground

- ABWR controlroom design development.

- ABWRcontrolroomdesign

- Design certification Issues

- Keyfeatures(Ill)

- Fixedinventory(II)

- Workload and control room staffing (VI).

- Prototype (IV)

- DSER items (V)

- (Japan) designprocess (I) 4

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l ABWR General Design Objectives Eliminate past problems / design issues-Enhance public safety / plant investment protection

- Enhance' plant operability, availability, and maintainability

. improve man / machine interface Control / minimize costs Adapt state-of-the-art technologies l

Utilize proven designs e

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Specific "MMIS" Design Goals i

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Eliminate trips / system unavailability due to human error / single instrument channel failures Minimize burden on operator

-Human engineered interface

- Reduce " manual" data processing Minimize burden on maintenance staff

-Improve self-diagnostics / fault indication

-Simplify servicing j

-Minimize equipment

-Minimize spare parts inventory Provide load following over 50% - 100% power l

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ABWR DESIGNDEVELOPMENT 9

1978-79 ConceptualDesign GE-Ledadvanced engineering team Participation by worldwide BWR manufacturers and AEs 1980-85 Design Development & Confirmatory Testing GE/Hitanhi/Toshiba joint technical effort (common engineering) 1986+

LeadProject(s)in Japan P

MAR.MS2GSt-5

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ABWRSTATUS TEPCO proceeding withleadunits

-Kashiwazaki6& 7(K60)

-GE)Hitachi/Toshibajointventure

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-projectschedule licensing application 19M KMcommercialoperation 1996

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KRcommercialoperation 1997 GE to supply nuclear steam supply, fuel, turbine / generators Hitachi/Toshiba to supply remainder of totalplant L

- Toshiba to supply main control room on KM l

- Hitachi to supply main control room on KR v

KE)7 designs are to be the same down to level ofprocur9d equipment

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- common K6/7 designs developed through common engineering a

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PRE-1986 CONCEPTUAL DESIGN A CTIVITIES i.

Produced an advanced controlroom design concept

- extensiveplant-wide automation 4

- advancedtechnologiesforMMI (e.g., touch screen CRTs) 4 I

- large overview displayboard 1)

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ABWR CONTROL COMPLEX DESIGN OBJECTIVES 1

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Provide an organization and arrangement of control center modules to maximize simplicity ofplant control' Optimize the quantity of data, and the method of data presentation,

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to improve operator response time and reduce the potential for operatorerror Integrate operator interface functions for allinterfacing systems to provide a uniformity in function and appearance Incorporate human factors criteria into allaspects of control centerdesign 1

AtAR M9 209-8

t COMMONENGINEERING i

Development of (VISION) design process and procedures

- industry codes, standards and guidelines

- fullscope ofdesign andproduction plantautomation software design and V&V human factors

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- reflects the iterative design process necessary over the complete design andproduction cycle

- incorporates customer (user) review and design inputs consistent with ALWRmodel Development of common designs that are independent of vendor's equipment

- consistent with US design certification program MAR %19 20's?- 9

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"MMIS" DESIGN AND IMPLEMENTA T!BN PROCESS i

Comprehensiveprogramplan

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- Systemfuncdonalandperformancerequirements 1

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- Functionallocatiowtaskanalysis

- Hananfactors/ Man-Machineinterface

- Hardware / software design VeriHcationandvalidation

- O&ntfpersonnelrequirements l

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' Exhibit 41, Proposed structure for control room design.

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Operator workioadanalyses l

Evaluation of automation scope i

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- Team of veteran operators 4

Results fed back into ABWR common engineering designs l

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i R&D-OPERATING CREWSIZE

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Evaluationofreducedstaffsize

- Controlroom operating crew of seven for common two-unit controlroom Adoption of" evaluation"goalfor one man operation

- (later embraced in the ALWR requirements) a Conclusion to maintain current staffing level

- ABWR design certification in compliance with 10CFR50.54(m)

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two Senior Reactor Operators and two Reactor Operators

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in agreement with ALWR requirements i

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R&D-CRTSCREENS i

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- NUCLENET, PODIA,NUCAMM l

- otherindustries Evaluation ofcharacteristics I

- formatflexibility

- ease of access i

- spacerequirements i

- reliability 3

MAR 119 242-12

I R&D -LARGESCREEN DEVICES Technologies

- large video screen projectors

- lightemitting devices

- flat displays (e.g., liquid crystal, plasma)

Evaluation of characteristics

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- contrast

- legibility

- resolution P

- colors

- visibilitythroughoutthe controlroom

- speed

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R&D-ALARM SYSTEMS i

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.t Operatorsaturation 1

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4 Alarm hierarchization P

I Alternate presentation methods and media i

Elimination ofunneededalarms masis2as-n

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Numberofoperators atconse!e i.

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R&D -FLATPANEL DISPLAYDEVICES Technologies D

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- plasma

- liquidcsystal 1

Evaluation ofcharacteristics

- legibility

- brightness

- colorcapability

- contrast

- reliability AL1RL19 2G2-16

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- durability 1

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R&D-AUTOMATED PLANTOPERATIONS 1

Operatorworkloadanalysis l

Operatorfatigue Speed and reliability of automated systems l

Scope of automatedoperations

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Symptomatic Emergency Operating Procedure Guidelines MPL A60-3010,23A6146 2.

Plant Integrated Operating Procedures. MPL A60w-3020 1.

Approach to Cnticality (23A6169AA) 2.

Heatup and Pressurization (23A6169AB) 3.

Turbine Startup and Generator Synchronization (23A6169AC) 4 Power Ascension and Power Chan9es (23A6169AD) 5.

Unit Shutdown to Unit Off-Line, Main Condenser Available (23A6169AE) 6.

Cooldown to Cold Shutdown, Main Condenser Available (23A6169AF)-

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Cooldown to Cold Shutdown, Maln Condenser Not Available (23A6169AG)-

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UnN Off -Une to Hot Standby or Hot Shutdown (23A6169AH).

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Maintalning Hot Stanciby or Hot Shutdown (23A6169AJ)

10. UnN On-Line from Hot Standby or Hot Shutdown (23A616SAK) 3.

NSS System Operating Procedures, MPL A60-3030 1.

Nuclear Soiler System (23A6179AA).

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Reactor Recirculation and Flow Control System (23A6179AB) 3.

Rod Control and Information System (23A6179AC) 4.

Control Rod Drive System (23A6179AD) 5.

Feedwater Control System (23A6179AE) 6.

Standby Uquid Control System (23A6179AF)J 7.

Neutron Monitoring System (23A6179AG)

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Reactor Protection System '(23A6179AH) 9.

. Steam Bypass and Pressure Control System (23A6179AJ) l

10. Residual Heat Removal System (23A6179AK)

11. High Pressure Core Flooder System -(23A6179AL)

12. Reactor Core isolation Cooling System (23A6179AM)-

13. Leak Detection and isolation System (23A6179AN)

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15. Fuel Pool Cooling System (23A6179AR)

16. Suppression Pool Cleanup System (23A6179AS) 4 yP.AR/3 3/7/90 y

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Automation Design Approach

- Operating procedures developed and task analyses performed

- Based entirely upon manual operation e

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- Candidate items for automation identified System level. sequence master control functions developed

- Simple safety system operations not automated Tedious or repetitive operations provided with new automated functions

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- Automated control rod operation

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Breakpoint control Iogic incorporated

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L Implementation of Automated Operations L

Top level " power. generation control system" (PGCS) function l

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- Based upon proven PGCS design in recent Japanese BWR plants Automati'.; mMe l-

- PGCS performs plant operations l

- PGC8 sends mode change commands and setpoint changes to L

system controllers

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- Operator controls status of safety system l

- Operator monitors and controls continued progression of automation operations Semi-automatic mode

- PGCS monitors plant operations and provides gu.Jance.

j Manual mode ua..,,,,,u s,-

Plant Automation Operation j

Operator can start /stop automated operatic n at anytime Operation automatically reverts to manua' mode in event of major plant upset (e.g., scram)

-LSelected routine post-scram operations are automated at the system level to reduce operator burden Individual systems monitor operational status.of the plant

-automation (PGCS) function and revert to manual if failure i

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. Compact low profile configuration Operator seated while performing all functions j

i Basic arrangement

- Normal plant functions performed in central area of console j

- Safety. related (NSS). functions on left wing

- BOP functions on right wing Color-graphic CRTs provide a primary operator interface

- Touch screens provide direct control of nonsafety equipment.

- Any display may be selected on any CRT

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Flat display devices LDisplay controllers independent of process computer Touch control capability

- Applied to both safety and nonsafety systems

- Safety, system equipment qualified Class IE

- Three divisions of ABWR safety systems have two. flat displays per division

. Hard' switch panels-

-: Facilitate faster access

- System sequence master control functions

- Reactor mode' switch

- Manual scram.

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~:'j l ALLOCATION OF FUNCTIONS MONITORING AND CONTROLSJ

_ l Control and Monitoring Functions Allotment of Functions-l Hardwired switches

. Manual' starting and resetting of.

~l safety systems,.--

• Automation console,-

• Manual starting of emergency-;

backups,1

+ Master switches for subloop?

automation, Flat displays with touch controls --

• Individual controls of safety

~ system components, -

+ L neup display of normal eu displays of safety-systems,.

CRTs with touch controls

. Monitoring of normal systems.

IndMdual controls of; components, -

• 11ndividual alarms,;

• i Automation;1

• Lineup display of_ safety systems and surveillance guidance.:

1:

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displays.

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_ plant safety status, ;.

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. performance summary, -

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--Important alarms

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SELECTION OF MAN-MACHINE INTERFACES OF CONTROL FUNCTIONS CKT-27 3/6/90

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- or SAFETY 4E.ATED SWITCMES TO -

OPEAATOR CONTROL GONSOLE

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s LARGEDISPLAYPANEL -FEATURES Fixedmimic ofkeyplantparameters

- seismicallyqualified

- dedicateddisplaycontrollers i

- systemstatus

- safety parameter display system (SPDS)

- post accident monitoring (PAM) variables

-- powergenerationsummary Variable displayscreen 1

- process computerdriven Fixedposition alarm displays

- plantlevelalarms

. - systemlevelalarms.

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Top-levelalarms fixedposition displays System-level alarms fixed position displays i.

o Subordinate alarms displayed on VDUs Alarm suppression

- Afode dependent

-- Consequential

- Redundant

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ABWR TOP-LEVEL AL ARM DISPLAY

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DESIGN CERTIFICA TION - STANDARD CONTROL ROOM FEA TURES r

(1) Single integrated control console 1

- staffedbytwo operators I

y

- Iowprofile forseated operators (2) Plantprocess computersystem on-screen control video display units k

(e.g., CRTs) j

- safetysystemmonitoring

-:non-safety system control and monitoring n

(3) Separate set of on-screen centrol video display units (VDUs) which are independent ofprocess computer system l

- divisionallyseparatedand 1-Equalified VDUs forsafety system santrol and monitoring (e.g., flat panel displays)

- another set of VDUs (e.g., flatpanel displays) for non-safety

}

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i DESIGN CERTIFICATION - STANDARD CONTROL ROOM FEA TURES (Cont'd) l l

(4) Control console dedicated function switches (5) Operatorselectable automation ofpre-definedplant operation sequences (6) Operator selectable semi-automated mode ofplant operations l

- providesproceduralguidance via the controlconsole VDUs (1) Conventionalmanualmode ofplant operations (8) Large displaypanel

- presents information for use by the entire controlroom operating staff.

(9) Fixed position display of keyplantparameters and major equipment status on the large displaypanel o

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. DESIGN CERTIFICA TION - STANDARD CONTROL ROOM FEA TURES (Cont'd) l l

1 (10) Separation of fixedposition displays which are safety related I

criticalplantparameters i

?

- Post Accident Monitoring (PAM) variables j

(11) Fixedposition displays are independent of the plantprocess computersystem.

J (12);Large displaypanelincludes large video display unit l

driven by the plant process computer system (13) Supervisor's console with VDUs formonitoring ofplant status a

VDUs (e.g., CRTs) driven by the plantprocess computer v

system i

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DESIGN CERTIFICA TION - STANDARD CONTROL ROOM FEA TURES (Con *'d) b (14) Safety Parameter Display System (SPDS) function provided on large displaypanes y

continuously displayed fixed position displays l

i (15) Fixed-position alarm tile on the large display panel (16) Alarm filtering andprioritization L

(11) Additionalalarminformationprovidedon controlconsole VDUs (18)J patialarrangement oflarge Display Panel, Main Control S

Console andSupervisor's Console i

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ABWR DESIGN.lMPLEMENTATION PROCESS (TYPICAL) 5.m#*'$M W hm ef w.?

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ISSUE-KEYFEATURES i

ABWR Control Complex design objectives useo as basis for selection offeatures

- experience fromprevious designs

- testsandevaluations Alternatives considered l

- tests and evaluations completed

- merits / demerits of each summarized

- choicesmade Evaluation criteria

- basedupon experience

- reflective of"new" equipment's characteristics

- developed during evaluation process

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ISSUE-KEYFEATURES(Cont'd)

J Operating experience a keyinput

- Maintain positive (e.g., maintain CRTs, low console)

- Eliminate negative (e.g., incorporate large Display Panel)

Interactive process forintegration into ControlRoom design

- testand evaluation ofindividualitems

- design developmentandevaluation

- mockups / prototype test and evaluation t

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ISSUE-FIXEDINVENTORY ABWR design development

- Large display panel (displays and alarms) overallplantstatus.

l nmitiple users continuouslyavailable

- Controlconsole(controls) emergency operations (speed / certainty) normaloperations (ease ofuse)

- Prototype developmentprocesa N

operatorinputx

" design developed consistent with objectives evaluations

-- Iprototype tests

ISSUE-FIXED INVENTORY (Cont'd)

U. S. Design Certification

- E0P/PRA operations analysis

- details ofimplementation of displays, controls and alarms 1

defined based upon ABWR design objectives l

1

- results compared to reference design t

4 k

i

1 ISSUE - WORKLOAD AND CONTROL ROOM STAFFING

.. i

.- i Original design development goal to support reduction in required I

opercing staffsize

- otherbenefits ofmaintaining existing staffsize identified (similar to ALWR Requirements Document)

Basis ofseatedposition controlconsole design

- operating experience atfive plants

- prototype testing E

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ISSUE-PROTOTYPE

^

u Scope

- prototype equipment

- panelmockups.

- full scope dynamic prototype for the defined test sequences.

- fullscope prototype of chosen configuration (included h

both proven andthe newfeatures)

. Test scenarios selected to challenge and test new features within the integrateddesign Tests addressed all modes of operation

- functionalallocation evaluated via operatorperformance,

. observations andfeedback'

Operator (re)trainingrequired with introduction of new features t

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4 ISSUE-DSERITEMS t

Valve indication provided as determined necessary by operations analysis s

Remote Shutdown System is entirely of analog equipment s

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4 ISSUE - JAPAN DESIGN IMPLEMENTA TION PROCESS e

1

Background

Practicalorientation less emphasis on theory, structure, documentation Evolutionaryapproach New features defined based upon 3xperience with previous designs and operators' comments BasicProcess Gathercomments from allsources

)

Design approach generated Engineers develop design concepts for widespread internalinformalreview engineers HFEexperts u

1

i i'

l ISSUE - JAPAN DESIGN IMPLEMENTA TION PROCESS (Cont'd)

BasicProcess(Cont'd)

- Developed conceptualdesigns dishibute:f forformalreview HFEexperts

(

Utilityengineers V

Utilityoperators

- Reviewers determine what to review and how Review results documented along with I

justification, as required i

- Review comments resolved thrcugh consensus

?

i-Harmonizing ofindividual viewpoints and design ophons

- Design approaches redefined / refined and process iterated

(

untilcompletion

}

- Final results accepted by group consensus L

ISSUE - JAPAN DESIGN IMPLEMENTA TION PROCESS (Cont'd)

Design standardization achieved through jointparticipation of equipment vendors in control room design development I

Basic design objectives guide allphases ofproduct development

- Design acceptance is by consensus of reviewers

- Key reviewers are the end users (i.e., operations and maintenancepersonnel)

Reviewpoints

- Informal reviews generally held at frequent intervals

- formal reviews generally held at scheduled completion of key design activities by consensus (judgement) of participants

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ISSUE - JAPAN DESIGN IMPLEMENTA TION PROCESS (Cont'd}

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l Final design detailed implementation completed through the same V

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- Directiordguidance of end user as part ofplant construction activities 3

Validation ofimplemented design performed at factory prior to l

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- Informalreviews during manufacture i

-Formalreviewofconfiguredsystem N

- End useracceptance obtainedprior to installation i

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Parallel trammg simulator actively provides feedback and l

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