View source for NRC-95-4498, Forwards Proposed Draft/Markups of Ssar Section 18.4 & Subsection 18.9.9.Encl 1 Submitted as Proposed Response to Listed AP600 Draft Safety Evaluation Rept Chapter 18 Open Items

{{Adams
| number = ML20086B558
| issue date = 06/30/1995
| title = Forwards Proposed Draft/Markups of Ssar Section 18.4 & Subsection 18.9.9.Encl 1 Submitted as Proposed Response to Listed AP600 Draft Safety Evaluation Rept Chapter 18 Open Items
| author name = Liparulo N
| author affiliation = WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
| addressee name = Quay T
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05200003
| license number = 
| contact person = 
| document report number = NTD-NRC-95-4498, NUDOCS 9507050453
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 37
}}

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i em 355 Westinghouse                Energy Systems Pinsburgh Pennsylvania 15230-0355 i
Electric Corporation NTD-NRC-95-4498                       !
DCP/NRC0355 Docket No.: STN-52-003               l June 30,1995                          ;
Document Control Desk                                                                                              !
U.S. Nuclear Regulatory Commission                                                                                 l Washington, D.C. 20555
                                                                                                                               .l ATTENTION:          MR. T. R. QUAY i

==SUBJECT:==
PROPOSED DRAFT / MARKUPS OF SSAR SECTION IS.4 AND SUBSECTION 18.9.9                                                                                         p v

==Dear Mr. Quay:==

Enclosure 1 is submitted as a proposed response to the following AP600 Draft Safety Evaluation
              -Report (DSER) Chapter 18 open items:
i Open item                                          Addressed By                                                 j i8.2.3.2-1                                         18.4.1 and I8.4.2                                           .[
18.2.3.2-2                                          18.4.2 and 18.4.3                                           -!
18.2.3.4-1, 4-2, 4-3, 4-4                           18.4.4 Enclosure 2 is submitted as a proposed response to the following AP600 DSER Chapter 18 open items:                                                                                                              ;
Open item                                           Addressed By 18.10.3-1 to 18.10.3-15 &                          18.9.9.1 and SSAR Subsection 13.2.1 (Rev. 3)
Meeting Open Item 2061 Meeting Open Item 2062                              18.9.9.1 through 18.9.9.4 i
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9507050453 950630 PDR     ADOCK 05200003 A                      PDR

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NTIANRC-95-4498 IX'P/NRC0355                                                                   June 30,1995 If you have any questions, please contact Steve Kerch at (412) 374-5104 or Andrea Sterdis at (412) 374-5292.
A N. J. Liparulo, Manager Nuclear Safety Regulatory And Licensing Activities
      /nja Enclosure 1:        Draft / Markup of SSAR Section 18.4 Enclosure 2:        Draft / Markup of SSAR Subsection 18.9.9 cc:    Jirn Hongarra             NRC 11HFB John O'llara              Brookhaven National Laboratory Brian A. McIntyre         Westinghouse (w/o Enclosures) l wm                                                                                              l

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TABLE OF CONTENTS                                                                      j!
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Section                                            Title                                                          h       ,"
18.4     MMIS Design Team .     . .........                .... . .... . .              .. ..           . 18.4-1    r.
18.4.1 Characteristics   .. . ....... ..                 ...      ..       ..........             18.4-1 18.4.2 Qualifications . .       . . ......... ...             .,. . .....             . . .       18.4-2 18.4.3 MMIS Design Team Role ........ ... ............                                  . . . 18.4-4 18.4.4 Human fpctorsgngineering Issues Tracking ..                     . .. ..                 . 18.4-8 18.4.5 Combined License Information Item . .................                               .. I8.4-10 i
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LIST OF FIGURES Firure No.                                Title                                                    Page.
18.4-1       MMIS Design Team Process .... ..... .. . .... . ......                      . . . . 18.4-9 18.4-2       MMIS Design Team Organization and Relationship to AP600 Organization                18.4-10 t
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otsarrev4\1804 R06463095     Revision: 4 W  W85tingh00S8                                                                        June 30,1995

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: 18. Human Factors Engineering 18.4      MMIS Design Team The mission of the man-machine interface system (MMIS). design team is to provide S :
develop'the main control room and ancillary control facilities (such as remote shutdown workstation =d !c=! p!=: :=tro! ". :i=:) that support plant personnel in the safe operation and maintenance of the plant. The MMIS; design team is responsible for coordinating the human factors aspects of the engineering, technical, and administrative disciplines associated with designing the structures, systems, and components that make up the main control room and ancillary control facilities !ce :cd ihmugh=: de p!=: The MMIS design team is part of the AP600 systems engineering function and has the same responsibility, authority, and accountability as the rest of the design disciplines. Figure 18.4-1 depicts the process used by the MMIS design team members. Figure 18.4-2 shows the organization of the MMIS design team and its relationship to the overall AP600 organization.
18.4.1    Characteristics The MMIS design team consists of a multi-disciplinary technical staff. The team is under the leadership of an individual experienced in the management of the design and operation of process control facilities for complex technologies. The technical disciplines andexp=ien=
of the design team include, the following:
                       --Hum = f ::cm engine:-ing'ngenemies Nucle = pcw= p!=: cperettens Instamentation =d :=*re! engin rin;;
Sy:; :=, engineering                                                                            ,
                       --Maintainability                                                                                  I Procedres development                                                                           j Comm=icaL..
Licensing                                                                                       j a--Neck = r=c = :ngineenng                                                                            I
                    .---Gempu:= :;yr,:::r: engin =in;; (hrd==e =d :;cf:== )                                               .
Trainin;; deve! pm=:                                                                          -l
* Technical project management
* Systems engineering
* Nuclear engineering
* Instrumentation 'and control (I&C) engineering
* Architect engineering
* Humaii factors engineering
* Plant operations
* Compmer system engineering
* Plant procedure development
* Personnel training
* Systems safety cugineering
* Maintainability /inspectability engineering
* Reliability / availability engineering o%sanev4\1804 R0443095   Revision: 4 T Westinghouse                                    18.4-1                                     June 30,1995

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: 18. Human Factors Engineering                                              i>
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5' 18.4.2        Qualifications In choosing the MMIS design team members, greater emphasis is placed on the individual's                                                                                                                                   {;
relevant experience to the specific discipline than on his-formal education. Alternative                                                                                                                                   i personal credentials may be ' selectively substituted for_ the education. and. experience                                                                                                                                 I requirements specified below."_~._:. :.. _d:":d"_'-                              .         ._                  .     ..y...~..'. . . .er-. .'. ._- . .. _ .". : .,^. :y".
                                                                                                                                                                                                                     . . .. ..^ .'Ihe professional experience h ic ': ::SS-d by of the MMIS design team as a collective ^ whole will satisfy the experience qualifications. The MMIS design team members have the following backgrounds:
                            ,c,,. . ._.     . . . ._. ., ._
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                     ?      Technical                           ject anagement                                                                                                                                                                       l A                                                                                                                                                     l Bachelor's degree l
Five years experience in nuclear power plant design or operations and three years of management experience
* Systems                         gineeringy -
Bachelor of Science degree Revision: 4 .w.rre,4wso4 no4.os3oos June 30,1995                                                                                       18.4-2                                                                            W       Westinghouse

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                       -    Four years of cumulative experience in three of the following ' areas of systems engineering: design, developrnent, integration, operation, and test and evaluation      ;-
* Nuclear Engineering                                                                          h Bachelor of Science degree Four years of experience in the following areas of nuclear engineering: design, development, test, or operations Instrumentation and Control (I&C) Engineering Bachelor of Science degree Four years of experience in hardware and software design aspects of proces's. control systems; familiarity with software quality assurance and control Experience in at least one of the following areas of I&C engineering: developmeng power plant operations, test evaluations
* Architect Engineering Bachelor of Science degree                            ,
                       -    Four years experience in design of power plant control rooms                               ;
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* Human Factors Engineering                                                                       i Bachelor's degree in       man    actors [gineering,[ngineering[ychology, or related science Four years experience in' the following areas of human factors engineering: human     -
factors aspects of human-computer interfaces (specifically,' design, development, and test and evaluation of human-machine systems for process control applications) and four years experience in human factors aspects of workplace' design (specifically,         l design, development, and test and evaluation ~ of workplaces)
* Plant Operations J    Current or prior senior reactor operator (SRO) license /SRO instructor certification
                       -    [ years experience in PWR nuclear power plant operations fe l
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                          =   Computer System Engineering                                                                      i
                             -                             lectrical   gineering or fomputer[cience or graduate degree Bachelor's in other engineering degreein[disciplin                                                    i Four years experience in design of computer systems and real-time system applications; familiarity'with software quality assur_ance and control
* Plant Procedure Developnent Bachelor's degree Four years experience in developing nuclear power plant operating procedures
                         =
Personnel Training Bachelor's degree
                                                                                                                   ~
Four years experience in the development of personnel training' programs f6r powt plants and experience in the application of systematic' training development methog
* Systems Safety Engineering                                                                      i
                                                                                                                            ?
Bachelor of Science degree or Bachelor's degree in Science                                {
i Experience in system safety engineering, such as thermal atmospheric' analysis,'
toxicology, radiological analysis and applicable OSHA limits                              j i
a  Maintainability /Inspectability Engineering Bachelor of Science degree or Bachelor's degree in Science Four years of cumulative experience in at least two of the following areas of power plant maintainability and inspectability engineering activity: design, development, integration, test and evaluation," and analysis / resolution of maintenance' problems s  Reliability / Availability Engineering i     Bachelor's degree Four years of cumulative experience in at least two of the following areas'of power plant reliability engineering activity: design, development, integration, and test and evaluation. Knowledge of computer-based, human-interface systems Revision: 4 owvemnu.o6ms June 30,1995                                         18.4-4                             T Westinghouse

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18.4.3      MMIS Design Team Role 4
W purpez cf Se '.1-MIS &:ign :=m i: to prev!& :echn!=! guid=:e, =d :c crganice; m= ge, =d review de deign of Se main +ontre! recm =d de == iated p!=: in:= faces, A mer :=: red apprc=h i: applied :c de deign. &velopmen: =d i np!:m=:::ica cf de M-MIS by de =mbem of 6 :=m ne-M-MIGwiesign-:== !=&r :: r ndivid=! >>ith prej$:: ==:gemen expe:i=ce in syMenwintegrati= =d in proj=:sth:: := cmp ==d de dixipline++: pre =n::d = Se M MIS desigrHeanw Each member of de M MIS & ign :== i&n:if.=, &velep:, =d previ&: :e Se t=m !=&r, guidanc+doeements;+peeifica:ic=, er cS= reference me:=i612: =e u=d in 6e neeutien of-4he :== reponsibilities:
The &:ign4eanueview: p!=:, repc:ts, =d & awing: == ia: d . 9. Se &;ign+nd &v:!cp m=: cf de M *!!S. Major hu== 5:erface ; !S Se p!=: =: 60 cc=i& red wiSi, $e were of de M MIS deign :=m Se M MIS de:ign :== !=&r reper.::e me p!=: & ig::
manager, The organization of the MMIS design team and its relation to the overall AP600 e,.idwi$
is depicted in Figure 18.4-2. De functional engineering groups may change'and reorganiai over time, but the basic organization of the MMIS design team is ittamed through the change.
The MMIS design team consists of a plant instrumentation and control system manager, advisors / reviewers team, core MMIS design team, and MMIS technical lead. De technical disciplines described in subsections 18.4.1 and 18.4.2 are organized by functional engineering groups within the core MMIS design team. The . core .MMIS design team' and the advisors / reviewers team report to the plant instrumentation and control system manager. He MMIS technical lead works in the Man-Machine Design group and reports to the plant                           '
instrumentation and control system manager through the manager of the Man-Machine Design group, The plant instrumentation and control system manager is' responsible for the design of the AP600 instrumentation and control systems.which include the MMIS. _ The plant instrumentation and control system manager reports to the ~AP600 project manager.                          -
f                                               De manager of the man-machine. design group, who performs the function of technical project management for the human factors engmeenng design process, is ~ responsible for the overall MMIS design and for integration of the MMIS design with the overall plant design.
                                                                                                                ~
The ' advisors / reviewers team is responsible for overseeing the general progress of the MMIS design, providing guidance to individual groups within the core MMIS design team, reviewing and providing comments on documents, specifications, drawings, etc., pertaining to the MMIS design, and providing supplemental expertise in particular areas of design. He responsibility of the core MMIS design team is to produce the detailed design of the MMIS. The man-     .
machine       gn group is responsible for the functional design of the man-machine interfaces in the h      IS, main control room and workstation ' layout (ergonomics), controls, the information system (displays), the wall panel information system, the qualified data processing system, the alarm system, and computerized procedures system design and specification. The responsibilities of the MMIS technical lead include coordinating the technical work of the o Wamv4u 804 R04-06ms     Revision: 4 W W85tinghCUS8                                   18.4-5                                      June 30,1995

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various. functional engineering groups, providing the administrative'and technical interface        ,
between the various functional engineering' groups 'and the advisors / reviewers team, and        (_
tracking the identification and resolution of human factors engineering design issues through    .)
operating' exp,erience n: view, The responsibilities of the individual technical disciplines described infubsections 18.4.1 and 18.4.2 can include, but are not necessarily limited to, the
[F ensuing list.
* Technical Project Management Provide central point of contact for management of the human factors engineering design and implementation process Develop and maintain schedule for human factors engineering' design process
* Systems Engineering Provide knowledge .of the : purpose, technical specifications, andEoperating characteristics of plant systems Provide input to human factors engineering task analyses                               -
                          -     Participate in development of procedun:s and scenarios for task analyses, conceptual tests, and integrated system validation                                                ,
* Nuclear Engineering                                                                          'i Provide knowledge of the processes involved in reactivity control and power gener. tion                                                                            !!
                          -     Provide input to human factors engmeeting task analyses Participate in development of scenarios for task' analyses, conceptual tests, and    -
integrated system _ validation i
f    Instrumentation and Control _ (I&C) Engineering                                                   i l
                          -     Provide knowledge of control and display hardware design,' selection, functionality, and installation
                          -     Provide input to software _ quality assurance programs Participate in the design, development, test, and evaluation of the MMIS
* Architect Engmeermg Revision: 4 ow-mac,enotawes June 30,1995                                        18.4-6                            T Westinghouse

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Provide knowledge of plant component layout and the overall structure of the plant         l including design characteristics and performance requirements for containment building, ' control room, remote shutdown area, and local control stations             b i.
Provide input to human factors engineering' task analyses Participate in development of scenarios for task analyses, conceptual tests, and integrated system validation a    Human Pactors Engineering Provide knowledge of human psrformance capabilities and limitations, humaa factors design and evaluation practices; and human factors principles, guidelines,         !
and standards
                                                                                            ^
I
                        -     Develop and perform human factors' analyses and participate in resolution of human factors problems                                                                           l
* Plant Operations Provide knowledge of operational activities relevant to' characterizing tasks"in4 environment and development MMIS componentsh procedums, andj training programs Participate in development of scenarios for tasks analyses,' conceptual tests, and integrated system validation i
* Computer System Engmeermg                                                                        1 Provide knowledge of data processing required for MMIS ' displays and controis Participate in design and selection ~ of computer-based equipment such as displays    -i and controls
                        -     Participate.in.. development of scenarios for task analyse's,1 conceptual tests, and integrated system validation, particularly those involving failures of the MMIS data processing systems
* Plant Procedure Development
                                                                       ~
Provide knowledge of operational tasks and procedum formats Provide input for development of emergency operating procedures, computer-based procedures, and training systems ownso4 amms            Revision: 4
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                                                                                                                         ;i 2    Participate in.' development of scenarios for task analyses,' conceptual' tests, and    ii integrated system validation                                                            ji i!
                     -     Personnel Training                                                                           lI Develop content and format of personnel training programs Participate in development .of scenarios for task a'nalyses, conceptual tests, and integrated system validation
* Systems Safety Engineering
                           -    Identify safety concerns Perform system' safety hazard ar.alysis such as thermal. atmospheric analysis; toxicology analysis, and radiological analysis a     Maintainability /Inspectability Engineering                                             :
                           -    Provide knowledge of maintenance, inspection, and surveillance activities Provide input in the areas of maintainability .and inspectability Support design, development,'and evaluation of control room and 'other MMIS components                                                                             ,
Participate in development of scenarios for task analyses, conceptual tests, and integrated system validation l
3
* Reliability / Availability Engineering Provide knowledge of plant system and component reliability'and availability and     -
asassment methodologies                                                                    1 I
Provide input to design ~of MMIS' equipment                                                l 9    Participate,in development'of scenarios for task analyses,- conceptual tests, and          !
integrated system salidation                                                               l l
18.4.4       Human factors engineering Issues Tracking                                                             i Tracking of human factors (human factors engineering) issues.is accomplished within the framework of the overall plant design process.- Various methods are used to identify, track,          ,
resolve, and document design concerns and issues, including human factors engineering issues,         l In this manner, human factors engineering issues are addressed in the same way as those for           ;
other disciplines. The methods' used are the design configuration change control process, the Revision: 4 os m,4siso4 no4a3ov5 June 30,1995                                          18.4-8                           W  W85tingh00S8 1

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                                                                      /W r                              m sign     view (DR) process, the[ystem pecification focuments (SSD), and the Advanced ight     ater Reactor Utilities Requirements Document (URD) compliance database.
I The design configuration change control process ~ is used to control and implement a change                                                                     h to the design.' It is used when the design to be changed has been previously released in a document for project use and placed under configuration control.- A design change proposal is the vehicle used to initiate and document review of prop,osed design changes'.~ Design change proposals include identification _of impacts lof the proposed design change from affected functional groups. In some instances, human factors engineering issues are addressed by the initiation of design change proposals ;whereas in other instances, they are addressed as a consequence of human factor engineering review of design change proposals originating from other disciplines. Design change proposals are maintained in a data base that is used to track the status of each design change proposal from initiation through implementation and closure.
1 Another method of identifying and tracking design issues.is through the. design" review process. Original designs, as well as major design changes, are subject to the design review process. For each design review,'a design review data package is me -@It includg checklists, including one specifically addressing human factor engineermg questions,1whi$
are used by design review committee members to aid their review.iFor each designLiss@
identified through the.use of checklists or otherwise, an . action' item is initiatedf ant                                                                         ;
documented through an action item chit. . Once initiated, all action items are tracked until                                                                       i ciosure, including appropriate documentation. 'Ihe design cannot be implemented in the field, except under extraordinary circumstances, until all action items are satisfactorily resolv'ed and docamented. If a design has any open design review action items associated with it, then the                                                          ~
Combined License applicant must be so informed. For preliminary and intermediate design reviewsAra action items may be deferred to a more appropriate, subsequent design review; The resMh *ity of tracking open design review action items is assigned to the responsible                                                                       ;
design manus (i.e., the manager responsible for the system reviewed) and program control and administration.
I Both the design configuration change control and the design review methods of identification                                                                 -l and tracking of human factor engineering design issues occur at some time after the' system                                                                        l design is in the configuration control process. .puman factor engineermgLissws that are identified earlier in the design of a system are tracked by includinfthem in the respective                                                                        l System Specification Document (GSD). This is the third method used to track design issues,                                                                         !
including human factor engineering issues. Requirements have been estabbshed for preparing                                                                         !
SSDs for instrumentation and control (IAC) systems and man-machine interface systems.
human factorfengineering issues related to the MMISs (i.e.. .thelalarm: system, plant information system, wall panel information system, controls, computerized procedures system and the qualified data processing system) are tracked by entering them into the respective                                                                         '
functional requirements 'and design' basis document as a performance; requirement or a functional requirement. For human factor engineering issues related to systems'other than MMISs or 1&C systems (i.e., fluid systems), the human factor engineermg/MMI considerations and issues are tracked by entering them into the appmpriate sections of the SSD.
owmausos ano6ms                                                                     Revision: 4 W85tifigh0US8                               18.4 9                                                                                                June 30,1995

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The last method of identifying and tracking design issues is through 60 use of the URD                    :
compliance database. De URD compliance database is used to document the compdance of the AP(00 design to the URD requirements. Design requirements, including human factor engineer.ofMMI requirements that are contained in the URD are entered as a record into the URD compliance database. He respective design engineer is responsible for recording, tracking, updating, and resolving the compliance status for each of his requirement:.. . A compliance database administrator aids in the contrcl and administration of this database.
i As indicated in the descriptions above, the responsibility of tracking design issues is assigned to various persons depending on the specific method. For human factors engineering issues, the MMIS Rchnical lead is the one central person who is assigned the responsibility of tracking the human factors engineering issues from initiation through resolution.
18.4.5     Combined License Information his section has no requirement for information to be provided in support of the Combined License application.
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5    . 18. firman Factors Engineering                                                                                              :EE l
DESIGN IWL1TS MAN-MACHINE INTE.RFACE SYS1EM                                   M-MIS DESIGN TEAM ACYlSORS/ REVIEWERS A SPECIF1cALLY DESIONA1ED TEAM TRAINED IN;                                                     CORE IH4f2 DESIGN TEAM i
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                    . MeNeinaldityJlnspostdpHily ErM                           Conens Mn4empYeeeng a WAN EaE8ae*'*4                                         . hesentam opersesris end coneel Centere Dueurnest i
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                                     . nsas. hermeense Den oneunen
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                                     . Proved Ovesen compesAdgry in the Design
                                     . Verry Desden stages Figure 18.4-1 M. MIS Design Team Process Revision 4
[ Westingh00S8                                                                                                    June 30,1995 XXXX

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* 18. li man Factors Engineering                                                                                   ~-t-+'
:t i-APS00 PROJECT MANAGElt 4
Pl&CS MANAGER
                                                                    -----               ADVISORSjREVIEWERS TEAll I           I                                         1                             1      ;
l                                  l PROCEDURCS l           MAN MACHINE DESIGN GROU>               CONTROL SYSTEW              lNGROUP                -
GROUP          l    ONCLUDING MMIS TECH LEAD >          l   ANALYSIS GROUP             l 13eplays                        I  . Functional Destyist      i I       . Aserene                         I     centre syenerne         i
                                            . cor.w.                          j l       .ex.       :- -
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                      . Domesse easseng                                                         . setwere Domien
                      . u .uss y a v                                                            . coatre sysiere Desey '
                      . Teek %                                                                  . Intepuden CORE M - MIS DESIGN TEAM M - MLS DESIGN TEAM Figure 18.4-2 M. MIS Design Team Organization and Reistionship to AP600 Organization Revision 4
[ W85tillgh0U$d                                                                                           June 30,1995 XXXX

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                                                                                                               =
    *    .18. Human Factors Engineering 18.9.9    The AP600 Training Program                                 O
                                                                                                      ~
Thefollowing activities, described or reference     re beyond the scope of design certijication:
* Development and execution of the training pmgram'for. the; hwnan factors engineering vertfication and validation test subjects
* The humanfactors engineering V&V
* Insights to the training progrbm for ope alorsl resultingfrom the human factors engineering V& V,for consideration by the Combined License applicant during their training program ~ development.
18.9.9.1  Introduction This =5c^ctier describec me procer us-d te design =d 'mple=nt me AP6^0 t-ddng progr= Se fecun !: en We =ln cont c' eem operater trddng progr=, cince $b :: ea h= ch=ged signikaatly                                                                            7
                                                                                                 ~
As~ stated hi /ubsection !13.2.1, personnel' training, is a: Combined Licenpapplicini responsibility. Combined License applicants referencing the AP600 certified design deve16p and implement training programs for plant personnel.; LInsightsLto thef training' program reaulting from the human factors engineering.V&V are available for considerationLby..the Combined License applicant during training program development; This section describes a' process for the design and implementatio'n of a~ training program that is directed toward the training operations personnel who participate as subjects .in the. Human Factors Engineering V&V in the AP600 simulator. Not only is'there;a need to have~ skilled            I operators for conducting the evaluation of the control room MMLS, there is ~also a need to develop a gro .of AP600 operator Subject. Matter Experts {wholare instrumental in'the -
developing       , ne Combined License applicant.tra!ning program.: LThe training procesa described here is intended to build on existing operational skills ^and experience of.the          .
subject-matter experts (such as reactor operator or cenior reactor operator license) to produce operations personnel who canfcompetently perform a range of tasks in the AP600 simulator.
Following are several differences between AP600 operations and the' subject-matter experts previous operations experience. These differences are an hnportant driverjn training the human factors engineering V&V operations personnel.
* The operation'of the passive safety systems is important t6; understand.TAlso'important is an understanding of the instrumentation and control systems architecture;
* AP600 interface design; especially the' requirement forlmore' interaction in: interface management (finding displays or controls). 'Also is.'an understanding.of the. alarm system, the wall panel information system, and the use of computer-based procedares is needed.
                                                                                .wm4um axams             Revision: 4 3 W65tingh00S8                                  18.9 81                                    June 30,19H

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    .                                                                                   18. Iluman Factors Engineering
        - - -                                                                                                                     i 1
                       . The AP600 approach to the presentation of plant state, which considers functional views               -
and physical views of plant state. l Tied to this dichotomy in the presentation of plant             -
state is the AP600 approach to decision making. in which the operator takes on a larger role in ensuring that the procedures are . appropriate and effective.                              ,
18.9.9.2       General Approach to Training Human Factors Engineering Operations Personnel
                                                                                                 ~
The design, development, evaluation, and validation of nuclear power plant training programs CP'& guided by the systems approach to training (SAT). The' AP600 approach to training the human engineering factors operations personnel, however,is less formal and does not require the systematic application of SAT. The most important objective for this. training program               ,
is to train operators to control the 'AP600 simulation well enough that the human' performance issues tied to the MMIS design are accurately assessed.;The V&V demonstrates that operators who are reasonably skilled with the AP600 control room MMIS can perform a range of tasks within the defined performance standards.
Instead of using SAT to guide the development and evaluation of training,'a performance!                [
based evaluation of training detennines that the trainees ha've ~ mastered the requisite _ skills:
This evaluation is tied directly to the V&V scenados. A' set of scenarios that bequire very similar operator skjlls as the V&V scenarios but have difrerences at the level of'operak actions __are ujigd JFor example,if the V&V plan calls for a small-LOCA event, apond "small-LOCA scenario that differs in'the presentation of initial symptoms, k ''* LN'A",r            ((
l es;!. , M $2 c:re ^' =%Ws usedh The operations personnel are considered to be sumciently trained when they are able to perform these_' training scenarios (performance criteria are established when the scenarios are defined). Note that this parallel set of scenarios
                                                      ~                                                                        '
is used in training only, not as part of V&V,
                                                                                                                               ,i The parallel set of scenarios will. aid ~in~ Identifying critical operator' skills and provide.a
                                                                                                                        ~
context for training activities. Most important, these scenarios allow a determination'to be                ,
made of when the operators have developed sufficient skills to conduct the human factors                    l engincedng V&V.- Finally, the training activities with.these scenados provide a mechanism     -
l for ' additional feedback on the MMIS designi _If there are elements of the MMIS that are             '
i difficult for the trainees to master, this may indicate that design refinements or modifications are required.
18.9.9.3       Recommended Training Practices                                                                              1 Subsection 18.6.6 offers the following descriptions of the AP600' operator:
A competent operator is one who is mentally ahead of the process that he controls.                    l
                             ...the operator must have an excellent mental 'model or image of the behavior of that process.
                             'Ihe operator is corninually evaluating ar d validating the instrument indications..;
                             #Ihe operator also uses his mental model to anticipate the consequences ~of' control actions _.and is determining if those actions are accomplishing their purpose.
Revision: 4 ow tre 4uswno4-o63095 June 30,1995                                            18.9-82                            [ W65tingh0US8
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: 18. Human Factors Engineering m --        N
:l Dese descriptions' portray an operator who is a somewhat autonomous decision maker that               h supervises the performance of plant systems. To a large extent, current training programs _ treat        i operators as users of procedures, and independent decision making is not really expected. De
                                          ~                                                                                 !
new' orientation 1to operations requires that the training; program' stress' decision-making
                                                                                         ~
1 aidllMind cognitive skills. In addition to geadng training more to cognitive skills, al number        .
of training principles (Reference 21) should be applied to this' training to enhance' learning effectiveness! De following recommendations. illustrate how these principles might be
                               ~
applied to operator training.                                                                            !
Provide a framework for job oerformance.c There is strong evidence that the' acquisition of new information is;most efficient when a strong. context is provided.9 %us, the training program needs to establish a broad framework of the orientation to operations / De operations            j personnel (V&V test subjects) have the traditional l operations framework in. mind.? %e new framework helps trainees give meaning to'and integrate new information.J Humans' rely heavily.on mental structures to understand the worldAThat is, new information is interpreted in the context of a meaningful context. Thus, by establishing.a new operations framework; new information can be interpreted in the context of the. requirements for AP600 operations; and learning is facilitated.
If there is no mental structure available to provide a context for nedinformationltwoltypbs              ;
of Icaming failures can occur. ; One, new information that..is. presented'without_ a;strotg context is likely to be forgotten. ; %e second type of. failure is the' creation lof " inert" knowledge. When new information is teamed without the context of how the knowledge is tied to the job, there is no link between factual knowledge and its use in a skill. jThis can lead to what is called inert knowledge.11nert knowledge enables one to select the correct. answer on a multiple-choice test or supply some appropriate words'when asked a test question lbut the tralace does not understand how the knowledge relates to other knowledge or how it is     ..
used in the comext of the job.' Inert knowledge is, therefore, useless forjob performance.
If the trainee has the appropriate context for' AP600 operations, new knowledge is more like19 to be retained and tied to jobikills. Derefore, one cady objective of this training program is to give the trainees a thorough' understanding of the operational _ philosophy and their role    .
in operations.
Use actual lob ' context to surmort training activities.EThe operational l"orjob," context in addition to establishing a framework for the broad set of skills to be trained, also should serve
                       ~
as a setting for; instructional activities.~ Bus,'the.; training program should present new knowledge (theory, control room operations) and component skills (measurement techniques, finely tuned control actions).within the context of their use in job taskskRese component skills and knowledge may be fatroduced in a context outside of the job setting (classroom),
but should be integrated back into the job context quickly.(by.use of simulation).
                                                                                                         ~
Factual knowledge must eventually take a procedural form,Tand therefore/ It needs;to be lategrated into task performance. : IsolMed factual knowledge and individual skills'can be given meaning by associating them with their function in the context of the job. De training program should continue to motivate learning by identifying the role'of the new knowledge o w usa mo m s             Revision: 4 3 WB5tingh0US8                                    18.9-83                                    June 30,1995

E!ERill!
  ,.                                                                                18. H man Factors Engineering        g O
H In'the context of the job. And, the training program should condnue~to support integration          -
1 of new knowledge and skills into larger, more meaningful, task.-                                    u
                          ~
Make decision-makine ' strategies explicit. Operators areTgiven much ofitheirequired knowledge in a classroom context, but . decision-making skills;are more than justhaving l
knowledge available. lIt is important in trainirg tggi g4li ed ;ct                    -
by le
                                         ~
offering'anfexplicit model. .:If one identifiesy operauonal go y set o e strategies, and the rules for applying those' strategies,'o.ne establishes a more appropriate set of instrucdonal objectives for decision-making skill The training progrcm offers an approach           ,
to skilled decision-making;; operators are shown how to employ functional and physical displays to arrive at appropriate diagnoses and select appropriate procedures.
Ensure that low. level skills reouire little attendon. TA new~ requirement for operators lis interface management.; Operators call up appropriate displays and ' controls, use, pointing devices, and manage other CRT-based functions. The; skills _ to operate-and manage the interface takes mental resources away from critical higher level skills (situation' assessment) since there are limitadons in' human attention and memory. iOne objective of;a; training program, is to manage the mental resources required for job performanced Both during training and for skilled job performance operators must handle low
                            ~
                                                                                           .n level skills coinpcic4 without using significant. mental resources. - There are several training techniques l.that clo support this goal.
One method is to isolate low-level skills l.that can be trained tota very high degree'of 1
proficiency, such as dispicy managementJ Training studies show that certain job skills can be trained to the point where they require virtually no additional' resources; these skills become " automated.". This type of training.~is referred-to. as ." automatically"f training Therefore, one goal of the training program is to isolate low-level sidlls carlyfand to apply training to reduce the mental resource requirements.                                               ;
                                                                                                          ~
improve evaluation technione. Linl addition to' measuring'~ skill level attainment,- the role of evaluation can be expanded in two ways to enhance training.3. First,6 valuation should take on 'a diagnostic role! . This ~ objective is facilitated byL having 'a' good model of.' skilled   ,
performance to which students can be compared.VIhe skilled performance model serves 'as a means for assessing and remediating student performance. ;For examplefmuch of the work in developing intelligent tutoring systems has focused on techniques.for describ'mg the student in terms of an expert model. The instructor or tutorial system requires this diagnosis'to determine the instructional focus and feedback provided to students as learning proBresses.
A similar approach toward student modeling and diagnosis for instructional remediation can be used.
A second way to expand the use of evaluation it to involve students in self-monitoring arxi self-dingnosis early in skill' acquisition.7A"modelLof skilled performance'is used to" aid students in critiquing their own performance when compared lto-ideal' performance.Mihis technique is introduced by having students critique others in' a group ~ setting.i Eventually, students learn to apply the same analysis to their own performance, Resision: 4 own.mmanoms June 30,1995                                        18.9 84                              Y W85tingh00$8
: 18. Iluman Factors Engineering vgg --
l' ll Introduce multiple form.9 of complexity durine simulator training (The simulator is a powerful             )'
training tool. ;The instructional value of simulation is that the task endronment can'bc structured carefully to . focus'a' trainee on a specific' learning;expedence.f One key to the effective use of simulation is to consider the range of experiences provided to students and to include several descriptions of complexity. L One. form of complexity;is the complexity             (
captured by the procedures. The NRS uses a number of quantitative attributes (NUREG 1021) to evaluate scenado complexity ;These include; number of crew critical tasks, ~ number of EOPs entered,'and number of major events./ Also included are attributes such as nember of components failures and'numberLof instrument malfunctions. 5 While these; quantitative                  -l attdbutes clearly add complexity to'a' scenario, there are also important cognitive elements in nuclear power plant operations that create difficulties for operators.. In
                                                                                            ' . many cases, the ability         ,
to respond to these cognitively difficult situations separates the highly skilled operators from            l the average operators. L A' catalog of situations that create these complexities is found in Reference 20 and includes the followingd
                    . Situations in which important indications can be incorrectly " rationalized away."Lihat is, indications that should be diagrade may be attributed to a consequence of a known              -l but less significant failure or of an automatic. action (shrink and swell).                j s.
                    . Situations in' which multiple faults mask each.other.                                      2         '
                    . Situations that deviate from operator assumptions or expectations.1 For example,Vsafety          $
system may fail to respond as demandedior human errors occur in carrying out control             !;
actions to mitigate a component or system' failure; This list identifies the more qualitative indices 'of scenario'complexityf 1he major ' point is that simulation scenados ast not simply a means to expose operators to a' set of experiences that                l are otherwise expensive or dangerous in the actual setting. Simulation scenarios should be                  i both systematic and explicit in their presentation lof the sources of complexity that can bc                l found in operations.                                                                                       j 18.9.9A      Training Insights Report                                                                             .
After the human factor engineering V&V' operations personnel are' trained'and.'the V&V is
                                              ~
completed, a report <ls. developed to pass on training insights to;the Combined License applicant. This report addresses a number of issues, including the following types.of issues; 1
Task and Skill Analysis. The Training' Insights Report offers guidance orfspecifying the range of operational tasks and the operator skills required.; Especially important is the analysis of the decision-making skiBs required by operators to be effective w       e h the MMIS.                    l Jrainine Guidelines.GTraining studies in' domains other than~ nuclear' power have put forth                 l training _techaiques and guidelines that;can improve the~ effectiveness and efficiency of                   j training. Training Insights report describes the ways in which training can be impmved. It                  l also describes appropriate uses of technology in training program design, development,'and
                                                                                                     .                          l implementation.
                                                                                   .ww.axosws              Revision: 4
[ W85tiligtl00S8                                    18.9-85                                   June 30,1997

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: 18. Human Factors Engineering                                            y
       --                                                                                                                                                                                                                                        ljJ,
                                                                                                                                                                                                                                                 }'
                                                                                                                                                                                                                                                 ~
vi Training Scenarios.1As described in subsection 18.9.9.3;it is critical to build 'a full range of l
complexity into simulator training. scenarios.~. The Training Insights Report provides insights                                                                                                                                 '
lnto the qualitative forms of complexity (Reference 20) that may be mort applicable to AP600                                       _
operations? These scenarios, can be incorporated into the Combined. License applicant's                                                                                                                                   d training program.                                                                                                                                                                                                         1 Performance Insichts/ The training program for human factors engineering ;V&V operations personnel and the V&V itself should provide insights into areas where operator performance is likely to be difficultE These experiences suggest the tasks that. operators have tmuble performinge and the tasks that are more difficult to_ learn. These.are important. inputs to                                                    . .
i training, and may impact . sequencing and/or emphasis in the; curriculum;
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Revision: 4 m-e. awes June 30,1995                                                                                                              18.9 92                                                                                     3 W95tingh00S6
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owam9 no4.ooo95                                     Revision: 4 W    Westinghotise                                                                                                18.9 93                                                                                              June 30,1995

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Revision: 4 ow.,re.4siso9.no4.06ms June 30,1995                                                                                                     18.9-94                                                                           W W85tinghouse

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18.9.10          Workstation Design                                                                                                                                                                                                             l 1
The following activities, described [or; referenced belowlare beyond'the[ scope of' design certification:                                                                                                                                                                                                                 l i
1
* The detailed design. 'includingLthe[dssignl documentation;;afltheioperator uvrkstations, supervisor verkstation, dedicated safetypanel, and remote shutdown                                                                   .
                                                                                                                                                                                                                                                    )i workstation                                                                                                                                                                                        ;i 1
* The korkstation i and controlJ 'roomi layout,; arrangement,Jandi environment (ergonomics) guideline document
                                                                                                                                                                                                                                                   - 1 This subsectioni''. . ^_^~..r'm-*.~:^      ..               .                  . ^ ' ' " ~ - "."...'.c.c~.^,,-..
                                                                                                      . ..                                   .               ,                ^~."..":~' .~. "._-'_"".md. contains a
_.                                                                        1 description of the operator workstations (A and B) supervisor workstation, and remote shutdown workstation.
The operator workstations, supervisor workstation, and remote shutdown workstation contain the displays and controls to start up the plant, maneuver the plant obtain full-power operation, and shut down the plant. Each workstation is designed to be manned by one operator.
Typical components housed by the workstations e.re be fe!!cJ'i .ginclude:
* Visual display units (seismic and nonseismic)
* Control display units (seismically qualified)
* Plant communication eq.4fpment
* Screen selector controls wwweauaws                                           Revision: 4 3 7,blin n40S8                                                                                           18.9-95                                                                                           June 30,1995

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: 18. Human Factors Engineering
* Composent selector controls                                                                   !
                                           . Keyboard The types ofinformation available on the visual display units includethe fc!!cvving-                .
* Functional displays
* Physical mimic displays                                  ,
a     Procedure displays
* Alarm support displays
* Special-purpose displays, The supervisor workstadon is idendcal to the operator workstadons, except that its controls are locked out. When the operator workstations are operable, no control actions are made from the supervisor workstation. The supervisor workstation contains both internal plant and external plant communications system;.
A Upon failure of either workstation A or wokstation B, the failed workstation is locked out, and the supervisor workstadon controls are unlocked. This modified workstadon configuration allows continuation of AP600 operation while maintaining independent, redundant workstations.                                                                                .
A safety panel is located between the operator workstations. Provided in this panel are the qualified plant information system visual display units and the dedicated safety system controls. 'Ihese visual display units are the only monitoring display devices in the main control room that are seismically qualified and that satisfy the post-accident monitoring guidelines of Regulatory Guide 1.97. A discussion of the plant information system is provided in Ssubsection 18.9.5. Positioned below the qualified; visual display units are           ;.
dedicated"~' " dred safety system controls switches, which are spadally and functionally           ,
dedicated to provide the operators with " single-step" safety system actuation capabilities.--A disce,sier cf the-4'unctic=          "a!!d!    S thb      t of centrol: E pro >!ded !n Subsection 18.9?.3.3.
The remote shutdown workstation is similar to an operator workstation.
The workstation design is implemented consistent with the workstadon and control room layodt, arrangement, and environment guideline document discussed in Ssubsection 18.8.2.1.3.4. The workstation design is verified and validated in accordance with the MMIS verification and validadon plan discussed in Ssubsection 18.8.2.3.
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i Revision: 4 ow.mausmau.osws June 30,1995                                                       18.9-96                            [ W85tingh00S8

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: 18. Human Factors Engineering                                                                                I 18.9.11   Main Control Area Design The following activities, described or referenced below, are be,~ond the ~icope of design certification:
* Detailed laput design of the main control area and supporting documen'ation   t
* Identification of specific communication needsfoFthe main con &ol'room operators
* Detailed design speiffication (performancea' ratfundtlanaliequiremehts)fo_r'the main control area 18.9.11.1 Mission Statement De mission of the main control area is to provide the support facilities necessary to enable
:yt     4               and facilitate the AP600 operators to monitor and control the AP600 efficiently and reliably.
18.9.11.2 Design Bases The human factors design of the main control area, including the performance requirements, the functional design, and the design specification, is established using die human factors engineering design and implementation process described in Section 18.8. Se design                   >
spedficat!cn for the nain cen'ec' re appers in Section !S.S. Human engineering is considered in the overall development of the area. The main control area is shown in the nuclear island general arrangement drawings in Section 1.2. A sample view of the main                j control area it-isas' incorporated in the main control room is shown in Figure 18.9.1-7.              i It is developed, consistent with architectural constraints of the auxiliary building, to house the control, data, communicadons, protection, and environmental equipment required by the main            !
control room operating staff. It includes space, furniture, and equipment for related ancillary activities. Rese related ancillary activities are evaluated in the same manner as the other           i activities described.
The design specification for the main control area includes identification of resources needed for the area. These include information, communication, hardware, and software needs.
Using the human factors design and evaluation techniques, needs are identified for systems and operator functions. These resources are provided in the area.
l For example, the communications needs for operators are established for within the area rnd between the area and the plant, the Combined License applicant management, outside                    i authorities, and the public.
De environinent of the area is specified so that man and machine performance is not degraded. This includes specification of design acoustic criteria. Air conditioning, heating, and ventilation are discussed in Sections 6.4 and 9.4.
I ow wup>ano4-oms          Revision: 4 3 Westingh0US8                                   18.9-97                                   June 30,1995

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,  ;    a .
: 18. Iluman Factr,rs Engineering The design includes adequate shielding, as discussed in Chapter 12. Adequate space, resources, and access are provided for maintenance, emergency equipment, and storage. The design criteria and features for fire protection are outlined in Ssubsection 9.5.1. Design criteria and features for the security of the area are discussed in Section 13.6.
The design specification for the main control area design also includes any other special                                                  i.
environmental considerations identified during the human factors engineering development                                                   i; process.
The design specification for the main control area includes periodic testing and equipment                                                 -
maintenance requirements related to proper performance of the tasks defined for the area. The items to be tested include alarms, displays, controls, audio and data communication equipment, and emergency and plant crisis response equipment.
w
             . o. i. s.. o.._.__._._..__2_2 n_ ,_. . _. . _.
                                              . . . . _ _ _       _ . .. ... r, ,_ _ c . .. . . n . . . i m. _ . . r _ _ _
a Ed' subsection contains-c &ccriptic af We funcdc= =d rece m=&d q='ificatic= for                                                             i the-men'bers cf be AP60^ ope = ting ::aff.--Ti ct ff-inclu&c 1e f^!!cring:           .
                                                                                                                                                                      ,  j' i
                                                                                                                                                                         }
a'         Reeng equipm=: cperator                                                                                                       ,  i-Reactor-operators
                             =         Senicr-reac4or-operators                                                                                                          j; finft-soprvi>iors                                                                                                                 i; Ehift-superviserls-c4erks                                                                                                        j, Sw!!c!nng =d tagging operator j
Shift-techmeal-advisor a----Reac4or-engineen 1
1 The &scripdc= cf me operater functic-                                                     =d q=lificatic= re bred e: ie 'eman engineering &c.!gn =d implemen'etion process & scribed in Sectie- ?S.S.
l l
The-personne! & scribed 8- $!r : etier ze required te succe'sfu!!y comp!:te a train!ng                                                         !
program-described in Subsec4 ice 18.9.9.
p.. o. . ,. .,
o..._._
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_.        _ .. . a n _ . e . , ot r i _. _. ._. _- _t ,.,.. .,_. _ r_ _.. _t....._..n.i._._..u._.a._
This subs etien centa!= descriptica ef be recc===ded c affing =d operating p d!csephy                                                5 fe' each of de fc!!cwing p!=: cdes' Strtup Forma! pcwer operation a-----Abawma! cp ration Emergenoy-operation
                                           . m.,..,,._a,.,
: u. s.
                                       "c' "hutdown Safe :hutdown Revision: 4 w.mauso9 no4-ooo95 June 30,1995                                                                            18.9-98                                             T Westinghouse

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: 18. Human Factors Er.gireering                                                                                                   ,
                                                                                                       ;-                            +.
Cc!d Mutdown "efee'ing.                                                                                                    I heaffsg-recommentiier =d creredng ph!!csephy are bred en me hum = engin^ering deden =d i plementation proces: described 4n Secden 18.8 =d We recc .m=ded operating Maff q=!!!ica !c= decoribed in Subsection 18.9.12.
     ! *.9.! t    '!d: Cr 're! ^_ = V:!!det!c:
The-main cen're! area va!!daden !: included = part of Se edittica cf We integrated M 'US discu=ed in-Subsectica 19 u.2.3.
18.9.4412 References
: 1. U.S. Nuclear Regulatory Commission 1979, " Human Factors Evaluation of Control Room Design and Operator Performance at TMI-2," NUREG/CR-1270 (Washington DC, United States Nuclear Regulatory Commission).
: 2. American Nuclear Standards Institute,1980, " Criteria for Accident Monitoring Functions in Light-Water-Cooled Reactors," ANSI /ANS-4.5-1980, LaGrange Park, IL.                        j
: 3. Rasmussen, J.,1986, "Information Processing and Human-Machine Interaction, An Approach to Cognitive Engineering" (New York, North-Holland).
: 4. U.S. Nuclear Regulatory Commission 1981B, " Guidelines for Control Room Design Reviews," NUREG-0700 (Washington, DC, United States Nuclear Regulatory Commission).                                                                                                     1
                                                                                                                                     !l 1
: 5. Smith, S. L. atx! Mosier, J. N.,1986, " Guidelines for Designing User Interface Software"                        I (Bedford, MA, Mitre Corp.).
1
: 6. ISA 1979, " Annunciator Sequences and Specifications," ISA-S18.1 (Research Triangle                          -4 Park, NC, Instrument Society of America).
: 7. EPRI Draft Report, "A Procedure for Reviewing and Improving Alarm Systems," MPR Associates, Apr.1983, EPRI Project 2011, Interim Report.
: 8. U.S. Nuclear Regulatory Commission 1983, " Instrumentation for Light-Water-Ceoled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident," Regulatory Guide 1.97, Revision 3 (Washington, DC, United States Nuclear Regulatory Commission).
: 9. Roth, E. M., Woods, D. D., and Pople, H. E., Jr.,1992 (in press), " Cognitive Simulation as a Tool for Cognitive Tasks Analysis" in Erconomics. a special issue on Cognitive Engineering.
ow m4usano4-o63095     Revision: 4 18.9-99                                   June 30,1995 W== Ubiii'E-iiOUSe

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        , , = _ _ . _
: 18. Human Factors Engineering i
: 10. Lesgold, A. M., Lajoie, S., Eastman, R., Eggan, G., Gitomer, D., Glaser, R., Greenberg, L., Logan, D., Magone, M., Weiner, A., Wolf, R., and Yengo, L.,1986, " Cognitive Task       f g
Analysis to Enhance Technical Skills Training .md Assessment," Technical Report              .
(Pittsburgh, PA, Learning Research and Development Center).
I
: 11. Means, B., Mumaw, R., Roth, C., Schlager, M., McWilliams, E., Gagne, E., Rice, V.,
Rosenthal, D., and Heon, S.,1988, "ATC Training Analysis Study: Design of the Next-Generation ATC Training System," HII Technical Report (Alexandria, VA, HumRRO International Inc.).
: 12. U.S. Nuclear Regulatory Commission 1982A, " Guidelines for the Preparation of Emergency Operating Procedures," NUREG-0899 (Washington, DC, United States Nuclear Regulatory Commission).
: 13. U.S. Nuclear Regulatory Commission 1980, " Clarification of TMI Action Plan Requirements," NUREG-0737 (Washington, DC, United States Nuclear Regulatory Commission).
: 14. U.S. Nuclear Regulatory Commission 1989B, " Lessons Learned from the Speci_al Inspection Program for Emergency Operating Procedures," NUREG-1358 (Washington,           y DC, United States Nuclear Regulatory Commission).
: 15. Schneider, W. and Detweiler, M., 1988, "The Role of Practice in Dual-Task Performance: Toward Workload Modeling in a Connectionist/ Control Architecture," in          l
                                         " Human Factors," 30, pages 539-566.
ll
: 16. Gentner, D. and Stevens, A. L., CA,1983, " Mental Models" (Hillsdale, NJ, Erlbaum).           f; i
: 17. Kieras, D. E. and Boviar, S.,1984, "The Role of a Mental Model in Learning to Operate a Device," in Coenitive Science, pages 255-273.
: 18. Collins, A., Brown, J. S., and Newman, S. E.,1989, " Cognitive Apprenticeship:             -
Teaching the Crafts of Reading, Writing, and Mathematics," in " Knowing, Learning, and Instruction: Essays in Honor of Robert Glaser," L. Resnick (ed.), (Hillsdale, NJ, Erlbaum).
: 19. Schneider, W. and Shiffrin, R.,1977, " Controlled and Automatic Human Information Processing: L Detection, Search, and Attention," in Psycholonical Review. 84, pages 1-66.
: 20. Mumaw, R. J. and Roth, E. M.,1992, "How to be More Devious with a Training Simulator:     Redefining Scenarios to Emphasize Cognitively Difficult Situations.
Simulation Multi-Conference: Nuclear Power Plant Simulation and Simulators," Orlando, FL, Apr. 6-9,1992, S'IE Paper 92 ISJ4-VIRTU P1 (Pittsburgh, PA, Westinghouse                     i Electric Corp., Science and Technology Center).                                                  l Revision: 4 oweaso%no+.o6w95 June 30,1995                                                     18.9-100                          3 Westingt10GS8

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8 i
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: 18. Human Factors Engineering i
211 Mumavi, R. A Swatzler, D., Roth, E.:M., & Thomas; W. A. (1994)._ " Cognitive Skill Training for Nuclear Power Plant Operational Decision Making,".(NUREG/CR 6126){      '
Washington, D._ C.: Nuclear Regulatory Commission.
: 22. Functional Design of the AP600 Computerized Plant Procedures System, WCAP-14388 (Proprietary) {WCAP-14389 Nonproprietary), May 31,1995.
: 23. AP600 Emergency Response Guidelines, GW-GJR-100) Rev. 0, May 31,'1995; 24,' Programmatic thvel Description of the AP600 Human Factors Engineering Verification and Validation Plan, WCAP-14401, April 13,1995.
                                                                                                         +
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3 W85tinghouse                             18.9-101                              June 30,1995}}