ML17276B013

Preliminary Control Room Human Engineering Design Rept. Four Oversize Drawings Encl.Aperture Cards Are Available in PDR

ML17276B013
Person / Time
Site:	Columbia
Issue date:	01/31/1982
From:	DAVALLE R G, MCGILTON C H, VAN EREM B J WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
Shared Package
ML17276B012	List: ML17276B010 ML17276B013
References
NUDOCS 8202020153
Download: ML17276B013 (177)

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PRELIMINARY CONTROL ROOM HUMAN ENGINEERING DESIGN REPORT January 1982 WASHINGTON PUBLIC POWER SUPPLY SYSTEM Nuclear Project Number 2 8202020i53 820iii PDR AOaCK OSO00WV'A'-',PDR

.0 PRELIMINARY CONTROL ROOM HUMAN ENGINEERING DESIGN REPORT.4.9 V.e~R.G.DaValle, Task Force Coor donator.H.Mc ilton, Task Force Member 6..~C B..Van Erem, Task Force Member January 1982 WASHINGTON PUBLIC POWER SUPPLY SYSTEM Nuclear Project Number 2

.

TABLE OF CONTENTS.1.0 2.0 3.0 4.0 5.0 6.0 6.1 6.2 6.2.1 6.2.2 6.2.3 6.2.4 6.2.5 6.3 6.4~6.5 Section Review Plan Management and Staffing Documentation and Document Control Revi ew Procedure HED Assessment Procedure Review Findings Control Room Panel Arrangement Control Room Wide Survey Reviews Wor kspace Environment Communications Computer Systems Indicating Light Review Annunciator System Design Review Control Room Panel Configur ation Reviews Control Room Enhancement Reviews Control Room Annunciator Panel Reviews~Pa e 1 2 6 6 8 11 12 14 14 18 19 20 25 38 40 54 APPENDIX: A Typical-Panel Configuration Review Documentation Package (P602 Benchboard)

B Typical Annunciator Panel Review Documentation Package (P602 Benchboard)

C WNP-2 Control Room Panel Pictures ATTACHMENTS' Typical Configuration Control Drawing (P602 Benchboard) 2 WNP-2 Control Room Arrangement Drawing 3 WNP-2 Control Room Design Review Task Force Schedule WNP-2-PRELIMINARY CONTROL ROOM DESIGN REPORT Review Plan WNP-2 concurs with the intent of performing a Control Room Design Review and has undertaken an aggressive program to complete a control room re-view in accordance with NUREG-0660.

WNP-2 methodology has been to pro-vide a dual program approach: 1)to participate as an active member of the BWR Owner's Group Control Room Design Review Program;and, 2)to es-tablish a WNP-2 Task Force for detailed assessment and development of recommendations, and to provide configuration control for the WNP-2 Con-trol Room.WNP-2 supports the BWR Owner's Group Program.The WNP-2 Task Force Co-ordinator is a member of the BWR Owner's Group working committee and has participated in the development of the Control Room Design Review Program and Survey Checklists.

Subsequently, WNP-2 Task Force members were trained on human factor's concerns and the BWR Owner's Group Program at a Owner's Group sponsored workshop.The Task Force has supported the pro-gram as members of Owner Group Survey Teams at Nine-Mile Point, Peach Bottom 2/3, and Pilgram Nuclear Power Stations.An Action Plan forming the WNP-2 Control Room Task Force was approved in April 1980.Upon formation, the Task For ce began monitoring the indus-try approach and participated in the BWR Owner's Group Program.Subse-quently, the Task Force utilized the BWR Owner's Group Program and train-ing to perform a Preliminary Assessment Human Factors Review of the WNP-2 Control Room.The review was completed in December 1980.The extent of the review was based on the degree of Control Room installation, avail-able trained operator s, review criteria and checklists, and the exper-ience of other utilities.

The preliminary assessment report was used both as a control room data base and to identify areas of greatest potential impact to project con-struction and schedule.Subsequent Task Force detailed reviews were pri-oritized and scheduled, documentation methods developed, and control room configuration controls established.

Initial review planning identified the need to: o Identify outstanding control'room changes.o Identify interfacing design work or reviews affecting the control room from a human factor concern.o Establish management control for integration of control room activities.

o Establish a configuration data base to control and integrate exist-ing and subsequent changes.

Engineering change logs and controlled panel arrangement drawings were reviewed.Outstanding changes were reviewed and"Holds" placed on re-lease for those changes that were of concern until panel configuration reviews were completed and controls established.

Project scheduling assigned full time personnel to develop and integrate control room engineering and construction schedules.

The Control Room Human Factors Program was integrated into the project schedule for visi-bility, management tracking, and integration with other control room activities.

.Supply System Project Engineering and Startup organizations identified personnel to coordinate and manage control room activities.

A Project Control Room Program Manager was assigned to monitor, coordinate and ex-pedite engineering and construction.management related activities.

A Startup Control Room Coordinator was assigned to monitor, coordinate, and expedite startup and construction activities related to the control room, and assist the Project Program Manager as needed.These management levels provided direct management support for the Task Force, integration of activities affecting control room design reviews, ensured support from other organizations or personnel as required, and provided the review and approval authority for Task Force Human Engineer-ing Discrepancy (HED)reports and corrective recommendations.

Configuration control methods were developed.

A configuration control set of panel arrangement drawings, were established.

All human factor changes, approved engineering changes, and proposed designs (such as RG-1.97, etc.)were incorporated.

Once established, all subsequent changes are reviewed by the Task Force against the configuration control drawings and established panel criteria.Panel changes require Task Force concurrence, and the configuration drawings are updated to reflect the approved change.Annunciator panel window layout configuration con-trols were also established.

Priority was placed on Task Force reviews of panel design layout and an-nunciator system design and layout reviews in order to establish the re-quired data base for configuration control.These areas were considered the most complex and potentially project impacting as to requiring addi-tional engineering and construction resources.

A schedule is attached indicating the relative sequence and time table of Task Force activities presently identified.

Schedule time frames are for survey reviews, HED preparation and development of recommended corrective actions.Engineering and contruction times to implement are not included.2.0 Mana ement and Staffin WNP-2 Project Management has retained responsibility and functional con-trol of the program to insure overall support to the control room review process, and integration with other studies, design changes, and related construction activities.

A Project Control Room Program Manager was as-signed to coordinate all control room engineering and construction activ-ities.The Control Room Task Force Coordinator reports to the Project Control Room Program Manager.Human Factor affecting activities within the control room are reviewed by the Control Room Task Force before implementation to ensure configuration control and integration between related activities.

Specific design and layout reviews include such areas as RG-1.97, RG-1.47, Safety Parameter Display System, new BWR Emergency Procedure Guidelines and Procedures, TMI related tasks, and other engineering changes.The Task Force Review Team was selected to ensure integration of Control Room related engineering design activities, plant operability, and con-struction.

To further augment the human factors experience obtained from involvement in the BWR Owner's Group Program, General Physics Corporation was contracted for human factors consultant services.Task Force Coordinator:

R.G.DaValle Bachelor of Science in General Engineering.

Experience includes fifteen (15)years in the nuclear industry.Five (5)years as a certified control room supervisor; three (3)year s in project design engineering of FFTF;eight (8)years with the Supply System in plant operations holding positions of Senior Operation Engineer, Super-visor Generation Administrative Services, and Nuclear Safety Specialist.

Member of BWR Owner's Group Committee on Control Room Design Review Program.Attended ten (10)day Owner's Group Human Factors Workshop Program.Participated in BWR Owner's Group Survey of the Peach Bot-tom 2 and 3 Nuclear Power Station Control Rooms.Responsibility to WNP-2 Project Management for NUREG-0660, Item I.D.l/NUREG-0700 Program Implementation.

Provide administrative and document control for the program;maintain working files and HED Log;ensure adequacy of Control Room reviews;coordinate license and AE engineering changes affecting the control room;perform assigned areas of review;.provide detailed overviews of Review Reports and HED Reports.Task Force Member: C.H.McGilton Bachelor of Science in Metallurgical Engineering, Graduate of Oak Ridge School of Reactor Technology, and NRC Licensed Senior Reactor Operator.Experience include eighteen (18)years in the nuclear industry.Four (4)years with the U.S.AEC;three (3)years as Shift Supervisor in the U.S.Navy Nuclear Program;two (2)years in engineering assignments involving BWR startup, operation, and re-fueling;eight (8)years at WNP-2, consisting of seven (7)years as WNP-2 Plant Operations Supervisor and presently, Manager of the WNP-2 Safety Engineering Group, which includes responsibility for coordinating plant technical specifications.

Attended ten (10)day Owner's Group Human Factors Workshop Program.Responsible for performing assigned areas of Control Room Reviews;providing operational reviews of Review Reports and HED Reports against available operational procedures and technical specifica-" tion;interfaces with experienced plant operation personnel; inte-grates human factors input into plant operations organization.

Task Force Member: B.J.Van Erem Graduate of U.S.Naval Nuclear Power School, Westinghouse Reactor Design School, and U.S.Navy Electronics and Advanced Electronics Schools.Experience includes twenty-one (21)years in the nuclear field.Eight (8)years in the U.S.Navy either aboard nuclear sub-marines or at naval nuclear test facilities:

five (5)years with the U.S.Atomic Energy Commission as Senior Inspector, Naval Reactors Division;two (2)years as Assistent Chief Nuclear Fueling Engineer with Morrison-Knudsen Company;one (1)year with Burns 8 Roe, Inc., as Senior Operations/Test Engineer on Nuclear and Fossil Station Test Programs: four (4)years as Senior AE Construction Superinten-dent at WNP-2: and one (1)year as Engineering Manager for the WNP-1 Instrumentation Contractor.

Presently, Senior Instrumentation and Control Engineer for the WNP-2 Architect Engineer.Participated in the BWR Owner's Group control room survey of Nine Mile~'Point Nuclear Power Station.Responsible for performing assigned areas of control room'reviews; integrating ongoing engineering changes between the Task Force and the AE: and providing detailed engineering reviews of Review Reports and HED Reports against plant design and engineering criteria.Task Force Member (Part Time): R.E.Green Bachelor of Arts in Business Administration, and Bachelor of Science in Industrial Technology.

Experience includes seventeen (17)years in the nuclear industry.Two (2)years as a Journeyman Electrician with the Atomic Energy Commission; nine (9)years with General Elec-tric Corporation as an Instrumentation and Control Safety System Design Engineer, which included design work on the WNP-2 Control Room Panels;and six (6)years with the Supply System as a Project Instrumentation Design Engineer and Senior Instrumentation Engineer.Attended ten (10)day Owner's Group Human Factors Workshop Program.Participated in BWR Owner's Group Survey of the Pilgrim Nuclear Pow-er Station Control Room.Responsible for performing assigned areas of control room reviews;providing NSSS dgsign and instrumentation review of Review Reports and HED Reports;interfacing with licensee's engineering staff and integrating engineering changes with the task force reviews.0 Startup Control Room Manager: G.J.Freeman Bachelor of Science in Electrical Engineering.

Experience includes fourteen (14)years in the nuclear industry and twenty-one (21)years in Industrial Control Systems.Experience includes checkout, startup, and operating assistance on complex instrument and electri-cal control systems, such as Recirculation and Feedwater Systems: BWR NSSS experience with General Electric as a troubleshooting spec-ialist in instrument and electrical control systems;and presently, Startup Control Room Manager responsible for coordinating WNP-2 Con-trol Room related Startup and Construction activities.

Holds pro-fessional license in Control Systems.Authorized by Project Management to review and approve Task Force HED corrective recommendations.

Provides Startup and Construction Impact Reviews and Design Coordination.

Gener al Physics Corporation:

Donald C.Burgy, Manager, Human Factors Engineering; Ph.D Candidate, Applied Experimental Psychology.

Human Factors Engineering and Man-Machine System Design and Evalua-tion.Areas of human factors expertise include systems analysis, information processing, man-computer interactions, performance eval-uation.training systems, and speech/non-speech communications.

Applied research background includes an emphasis in experimental d sign and methods, multivariate statistical analysis, mini/micro computer applications, and software psychology.

Experience in nuclear power plant control room reviews includes on-site field evaluations at North Anna, Surry, Zion, LaSalle, Susque-hanna (Advanced Control Room Design), and Zimmer Stations.Evalua-tions have included the application of current NRC Human Factors Guidelines and existing military standards to,control room designs as well as field and laboratory experimentation to validate criteria used in design tradeoff analyses.Robert J.Little: Staff Scientist, M.S., Industrial Engineering and Operations Research.Human Factors Engineer with General Physics involved with human factors engineering design reviews of nuclear power plant control rooms.Experience includes conducting and teaching human factors seminars;currently the Lead Human Factors Engineer for review of Georgia Power Company's Plant Vogtle Control Room, and Project Man-ager of the Human Factors Review for Long Island Lighting Company's Shoreham Nuclear Power Station.General Physic's Corporation is responsible for the review of as-signed control room areas;review WNP-2 Program Methodology and Doc-umentation Control;review Task Force Review Reports and HED Reports for adequacy of human factor concerns and recommended corrective action.

3.0 Documentation

and Document Control The Control Room Design Review Program involves the systematic use of a substantial number of existing documents and the preparation of new mat-erials to record and document reviews.Reference materials, review re-ports, Human Engineering Deficiency (HED)forms, and other working docu-ments were used.These enabled the Task Force to record review results, provide a design data base, identify and track HED's and resulting recom-mendations, and provide a document trail for traceabi lity.A data base reference library or access to reference material was estab-lished.Material included those noted in NUREG-0700 and.in addition, industrial reports on Control Room Human Factor Studies, Preliminary Plant Control Room Human Factor Reviews and audit reports from other plants, WNP-2 outstanding design changes, emergency procedure guidelines and procedures from other plants, standard technical specifications, and related NUREG's, regulatory guides, and TMI related reports.Documents and forms are being prepared as each phase of the WNP-2 Control Room Review Program is identified and implemented.

Standard HED forms have been prepared to identify the location of discrepancies, describe their nature and priority, and provide a record of recommended corrective actions.Initial data base review report formats, prepared prior to HED" Report preparation, vary depending on the review process and data requirements.

Control and traceability of HED Reports, and their review and approval, are maintained through Task Force HED correspondence, Supply System HED Directives to the AE, and a Task Force controlled HED Status and Tracking Log.All correspondence is forwarded to the WNP-2 Controlled Site Files, and a working file is maintained in the Task Force Coordinators Office.Appendix A and Appendix 8 contains representative samples of different initial data base review report formats, standard HED Reports, and con-trol correspondence.

4.0 Review

Procedure 4.1 Control Room Survey A preliminary assessment survey gas performed by the Task Force Review Team using the BWR Owner's Group Survey program and checklists.

The re-view was completed in December 1980.The assessment provided a data base for scheduling further detailed evaluations and for integrating subse-quent HEO corrective recommendations.

General Physics Corporation has completed a survey of the WNP-2 Control Room using methodology and checklists developed by General Physics Cor-poration.Included in the survey was a review of the WNP-2 Task Force program methodology, documentation control and methods, and HED Reports with recommended corrective actions.Reports are being prepared by Gen-eral Physics Corpor ations to document their reviews.

4.2 4.3 Completion of open survey items not reviewable at the present time will be completed as design, construction, and operational readiness allow.Operatin Experience Review WNP-2 is a committed plant, in that it is not yet licensed, but the con-trol room panels have been fabricated'and installed.

Operating Exper-ience Review is thus limited due to the lack of hands-on experience of operations personnel, panel energization and turnover schedule.Operations personnel are used to the extent practical at this time.Dis-cussions of known existing control room problems and experiences from other plants are obtained from knowledgable operations personnel.

Panel concerns, reviews, and HED corrective recommendations are reviewed and discussed with operations personnel to provide as much operating exper-ience input as possible.System Functional Review and Analysis 4,4 Formal System Functional Review and Analysis is pending scope and format acceptance of the BWR Owner's Group Program.General Physis Corporation Methodology is also under review as an alternative.

To facilitate ongoing system and operability reviews, the Task Force is using available system operating procedures, operator training guides, vendor manuals, safety analysis reports, and other reference documents, to assess instrumentation and control adequacy.WNP-2 also supports the 8WR Owner's Group on preparation of symptom oriented Emergency Procedure Guidelines.

WNP-2 operations personnel are members of the working committee.

Draft WNP-2 Emergency Procedures were prepared and reviewed to define instrumentation and location require-ments.Findings were integrated with RG-1.97 and Safety Parameter Dis-play System requirements.

Control Room Inventory A reference set of data for control room instrumentation and'ontrols is available on computerized instrument and equipment lists, panel arrange-ment and engraving drawings, and other refer ence documents, such as, panel photographs, engineering drawings, vendor files, and other inven-tory documents.

A photographic mosaic log is planned in early 1982 to augment in detail the present panel photographs and to document the present panel design and layout.

4.5 Verification

of Task Performance Capabilities The adequacy of the work station areas to support the operator in perfor-'ance of his tasks is being evaluated by;verifying that required control room panel instrumentation and controls are available during the informal operating experience and system reviews noted in Sections 4.2 and 4.3, above;by performing human factor reviews and surveys;and by having an independant consultant, General Physics Corporations, audit, and review Task Force reports and corrective recommendations.

Formal verification will be completed upon completion of the system functional review and analysis portion of the program.4.6 Validation of Control Room Functions Validation of control functions by walkthrough of selected procedures and event sequences is scheduled prior to fuel load.Control Room construc-tion status, procedure preparation, and operator training does not allow for adequate verification at the present time.As an interim, operation-al experience, system reviews, and human factor evaluations, noted above, are used to validate HED corrective recommendations.

5.0 HED Assessment Procedure A review report is prepared by the assigned Task Force member.The re-view report identifies the area of review, concerns/problems noted during the review, and provides selected corrective recommendations.

The review report is distributed to all Task Force members.Each Task Force member reviews the report to ensure completeness and ac-curacy in their area of expertise.

The Task Force Coordinator overviews to ensure each area of review is adequate prior to preparation of.the HED Report.Each member is free to review the reports in each other's area of expertise as the need arises.'ll review reports and subsequent HED's are forwarded to General Physics Corporation for their review and comment as the review process continues.

A Task Force meeting is held to discuss the Review Reports, and resulting concerns and recommendations.

Review Report changes, additions and dele-tions are agreed to, and the report subsequently revised.All resulting concerns are reviewed against the HED Prioritization Criteria (See Appen-dix for sample HED and Priorization Criteria Standard).

Prioritization coding requires the unanimous agreement by the Task Force Team for each item of concern.All concerns are noted on the HED Report for document completeness and traceability.

The HED Report is prepared, concurred with by each Task Force member, and forwarded to Project Management.

Project Management has authorized the startup organization's Control Room Coordinator, responsible for coordinating control room startup and con-struction activities, to review and approve Task force HED Reports, and corrective recommendations.

Upon review of the HED Report, the Startup Control Room Coordinator meets with the Task Force to resolve areas of startup or construction impacting concern.All changes from the HED Re-port are unaminously agreed to and documented by Project Managaement Di-rectives to the AE.-8'-

All HED's are logged and tracked by the Task Force Coordinator in the HED Status and Tracking Log.Subsequent additions or changes are tracked by Project Directives to the AE and entry into the HEO Log.

Task Force Member I Perform Review I Prepare Review Report Assess Human Factor Concerns;Develop Recommendations Task Force Team Review Report Findings Assess Review Com-pleteness; Assess Operational Impact;Assess Engineering Impact Task Force Team Prepare HED Report Assess HED Discrepan-cies;Prioritize HED's;Approve HED Corrective Recommendations Startup Control Room Coordinator Review HED Report Assess HED Recommenda-tions;Assess Con-struction/Startup Impact Task Force Team/Startup Control Room Coordinator Resol ve Conf 1 icts Startup Control Room.Coordinator Project Directive to the AE Architect Engineer (AE)Prepare Detail Design Changes

.0~iFi di Section 6.1 Control Room Arrangement Section 5.2 Control Room Wide Survey Reviews 6.2.1 Workspace Environment

6.2.2 Communications

6'.3 Computer Systems 6.2.4 Indicating Lights 6.2.5 Annunciator System Oesign~Pa e 12 14 14 18 19 20 25 Section Section 6.3 Control Room Panel Configuration Reviews 6.4 Control Room Enhancement Reviews 38 40 Section 6.5 Control Room Annunciator Panel Reviews 54 SECTION 6.1 WNP-2 CONTROL ROOM PANEL ARRANGEMENT A.Operating Panels-Primary Area P601 Benchboard P602 Benchboard P603 Benchboard P800 Benchboard P820 Benchboard P840 Benchboard Reactor Core Cooling Systems (ECCS)Reactor Water Cleanup and Recirculation Systems I Reactor Control Systems Electrical Generation and Distribution Systems Main Turbine and Miscellaneous Systems Reactor Feedwater and Miscellaneous Systems FCDP Vertical Panel Fire Control Display Panel P851 Vertical Panel General/Summary Annunciator Panel B.Operating Panels-Outside Primary Area P672 Vertical Panel P811 Vertical Panel P812 Vertical Panel P813 Vertical Panel P814 Ver tical Panel P821 Vertical Panel P824 Vertical Panel P825 Vertical Panel P826 Vertical Panel P827 Vertical Panel P832 Vertical Panel Off-Gas Control Panel SGT and H2 Recombiner Panel;Division 11 Reactor Building H5V Panel Containment Vent and Purge Pannel Containment Monitoring Display Panel Main Steam Leakage Control Panel Cooling Tower Control Panel RCC and SW Control Panel Control Room HVAC Panel SGT and H2 Recombiner Panel: Division I RFW Heaters, Vent and Drain Panel Ps3P P82I p+peze P887 f'6'll PSIZ P 8I 3 P8//MCCf>CCtl+VTCR V~~C~4)~CS4.5mculdi77 Ce Al5oc.8'C OP roc-i,e,a P8 5 I o p city(fd ts CoN4olC, CiHfuTBA htc CR7~Q 4.o4ir)pt4

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-.ar hL 0 oe Phoo QCl p q4 MAP OF CONTROL ROOM SECTION 6.2 CONTROL ROOM WIOE SURVEY REVIEWS Workspace Environment Much of the workspace and environment could not be surveyed at this time.However, key areas affecting design and/or ongoing procure-ment are being inputed to the appropriate organization; e.g., infor-mation relative to procurement of emergency protective control room equipment has been forwarded to operations personnel.

Primary areas of reviews completed or ongoing in this area of human factors review are:~Accessibility of Instrumentation/Equipment reviews are included in the panel configuration reviews noted in Section 6.3 of this report.~Control Room manning and primary operating area designations have been identified in the WNP-2 Plant Administrative Opera-ting Procedures, and the information factored into the configu-ration and annunciator reviews noted in Sections 6.2, 6.3, and 6.5.General layout reviews of the primary operating area have commenced with the initial definition of items to be included in the work station area (desks, bookcases, file cabinets.carts, etc.).Initial layout definition is expected in early 1982.~Anthropometric data on all operating panels was obtained.Dis-plays and controls noted outside the guidelines were reviewed for relative importance and frequency of use.Specific reviews and recommended corrective actions were noted in the configura-tion reviews.One open item is that several controls with"J" type handles are located less than the three inch minimum clearance from panel edge on Panels P601, P602, P603, and P820.Resolution is pending development of switch and handle shape coding standards.

~Control room environment reviews cannot be performed until lighting, ventilation, and sound systems are energized.

How-ever, initial reviews of the lighting design was performed to ensure that normal, backup and emergency lighting systems met the basic system design human factors guidelines.

BENCHBOARD ANTHROPOMETRIC MEASUREMENTS (IN INCHES)Specifications Control Zone Min.Max.Oisplay Zone Min.Max.Benchboard Annunciator Foot Space-Oepth I Panel Height Min.-Max.-I Min.Max.I Min.Max.o BWR Program)30 60 o NUREG-0700 26 1/2 (1 30 68 27 90 28 25 88 90 P601 P602 P603 P800 P820 P840 27 38 35-.70 5.38 27 59 35 73 5.38 27 59 35 73 5.38 27 59 35 73 5.38 27 55 35 70 5.38 27 38 35 70 5.38 2 29.38 73 87 2 29.38 73 87 2.75 29.38 73 87 3.25 29.38 76 88 2 29.38 76 88 3.25 29.38 76 88 (1)Present control layout requires a 5 inch reach by a 5th percentile women to meet NUREG-0700 Guidelines (6.1.2.2.b).

~go.o~ssS (rNCVES)8EiVCHBOARD MEASUREMENTS P60'l, P602, P603, P800, P820, and P840 VERTICAL PANEL ANTHROPOMETRIC MEASUREMENTS IN INCHES I Control Zone Specifications I Min.Max.I o BHR Program J 42 60 o NUREG-0700 34 70(53)*Display Zone Min.Max.48 68 41(50)*70(65)*I Annunciator Height Min.Max.88 90 P811 P812 P813 P814 P821 P824 P825 P826 P827'832 P672 P851 P001 (1)P100 (1)FCP-1 FCP-2 FCP-3 26 30 30 23 30 37 33 26 26 32 37 34 26 36 28 39 63 60 76 62 59 60 55 62 78 58 64 70 52 28 30 44 72 47 65 65 59 30 60 76 53 45 71 72 79 72 71 72 71 66 7,1 77 81 68 47 82 77 82 80 81 76 76 76 82 78 53 80 43 30 51 87 87 87 87 87 87 87 87 87 85 87 84 84 84*Standard for controls/displays requireing frequent or precise use, or needed for emergency operations.

(1)Remote Shutdown Panels.

Communications Oue to the present state of construction, review of the communica-tion system design and functional testing of voice and audible sys-tems can not be completely performed.

Human factor design and func-tional reviews have been scheduled into three parts;1., Section 6.2 of NURfG-0700 will be forwarded to the responsible system engineer to review, check off, and provide a response back to the Task Force against the present design in early 1982.2.The Task Force will perform a review of the responsible engi-neer's findings.and if required, issue a Review Report, HED's, and prepare corrective recommendations, about August 1982.3.The Task Force and operations personnel will perform a func-tional review of the system, and complete any open items, prior to Fuel Load.

Computer Systems Due to the present state of construction, review of the computer system design and functional testing of displays, printers, and 0 other controls can not be completely performed.

Human factor design and functional reviews have been scheduled into three parts.1.Section 6.7 of NUREG-0700 has been forwarded to the responsible operations technical engineer to review, check off, and provide a response back to the Task Force early in 1982 on the system design.,2.The Task Force will perform a review of the responsible engi-n'eer's findings, and if required, issue a Review Report, HED's, and prepare corrective recommendations, about May 1982.3.The Task Force and operations personnel will perform a func-tional review of the system, and complete any open items, prior to Fuel Load.

6.2.4 Indicatin

Li ht Review The purpose of the control room indicating light review was to re-view all control room indicating lights for light test capability, bulb replacement ease, color coding, meaning, and function (normally on or off).All control room and remote shutdown panels were re-.viewed, not just the operating panels.The annunciator system was not within the scope of this review.1.Li ht Test Capability

-Only vertical Panel P634 (Recirculation Control Panel has a light t st capability.

The balance of the Control Room Panels essentially have no light test capability except for annunciator lights.Engineering has been requested to review the reliability of the indicating light system presently installed at WNP-2.Methods to improve the indicating light reliability will be evaluated.

Tack Force recommendations are scheduled about June 1982.2.'ulb Replacement Ease-Bulb Replacement ease and safety is acceptable.

No operator concerns were expressed, nor have any known problems occurred to date.3.Color, Meanin.and Function of Indicatin Li hts.1.Green/Red combinations are consistent in sequence and meaning except for a few isolated cases.Green meaning closed (valves)and de-energized (motors).Red meaning open or energized.

2.The use of Amber, Clear, White, Blue, and Miscellaneous Red and Green indicators are not consistently applied.Examples are: a)Clear lights are used on P631 to indicate trips.Other NSSS panels use white lights for the same pur-pose.This is also the case on redundant panels P609 and P611.b)In general.white lights on BOP panels are normally lighted.On NSSS panels, this is not.,the case.Some white lights are normally lighted and some are not normally lighted.c)Red lights on P672 are.used to indicate various modes of control.White lights are used for this purpose on other panels.d)Several panels (P611, P606, P609, P840, P602, and P821)have one or more lights of a color different than specified on engineering elementary drawings.

e)Nhite lights on some panels are used to indicate an abnormal condition while on other panels white lights indicate a normal condition.

The same is true for amber lights and red lights.An indicating light standard has been prepared and agreed to by the Task Force.Final approval is pending trial application in January 1982.The standard will ensure ,consistency of color code, meaning, and function.A data base was completed on all indicating lights in the control room and remote shutdown room.Each light was traced to its initiating point (valve position switches, circuit interlock, etc.).A light listing for each panel was prepared in a matrix format, listing the specific color, the meaning of tne light in a"lite" state, func-tion (normally on or off)and any pertinent remarks.At-tached is a matrix listing for Panel P602.A review of the data base light listing against the indi-cating light standard is scheduled to be completed in March 1982.Also, it was noted, that many lights do not have separate legend plates to identify their meaning.This presupposes operators will be knowledgeable on their meaning and ap-plication.

The present bulb-lenses are round dome shaped and panel space does not easily allow for proper legend plating.Reviews are under way to locate speciality manu-facturerss to design and prepare square headed engravable lenses to replace existing bulb lenses.If feasible, a Task Force recommendation is expected about March 1982.

WNP-2 CONTROL ROOM INDICATING LIGHT REVIEW PANEL P602 DATE 7-7-81 LIGHT COLOR MEANING REMARKS RRC Section Lights (1 each)above switches S106A and S106B (FW pump trip interlock reset switches).

Lighted-Indicates"reactor vessel low,water level and feed water flow is below minimum" interlocks are sealed in.Tnte lock initiates flow control val partial closure.a)Normally not lightec b)Possibly should be amber color.Lights (1 each)above switches S107A and S107B (total FW low flow interlock reset switches), White Lighted-Indicates"low total FW flow and RRC-V-60A(B) is less than 18%open" interlocks are sealed in.Interlock initiates RRC pump transfer to slow spec a)Normally not lighted b)Possibly should be amber color.Lights (1 each)above switches S108A and S108B (main steam lin pump suction lo+T interlock reset switches.White Lighted-Indicates"main steam line/RRC pump suction low+T" interlock is sealed in.Inter-lock initiates RRC pump trans-fer to slow speed.a)Normally not lighted b)Possibly should be amber color.Lights (1 each)above switches S110A and S110B (spare switches White None-associated with spare switch circuit.a)Switches (SllOA and S110B)and associatei white lights should be removed from pane.Lights (1 each)above switches S113A and S113B (Reactor vessel low water level interlock reset switches).

Lights (1 each)above switches S109A and S109B (flow control valve motion in hibit interlock reset switches.White Amber Lighted-Indicates"reactor ves-sel low water level" interlock is sealed in.Interlock initi-ates RRC pump transfer to slow speed.ighted-Indicates"flow control alve motion inhibit" interlock is sealed in.Page 22 a)Normally not lighted b)Possibly should be amber color c)GE dwg 761E791AD sheet 1 states li@t are amber, but sheet 9'shows'them as whiti a)Normally not lighted b)Should be amber as presently is, how-ever, is not con-sistent with rest of interlock seal in lights on panel.

WNP-2 CONTROL ROOM INDICATING LIGHT REVIEW PANEL P602 DATE Jul 7 1981.LIGHT COLOR MEANING REMARKS FEL-1 above switch S122 (Flux Estimator Bypass Switch)White Lighted-Indicates Flux Estima-tor Bypass Switch is"Normal." Light goes out when switch is placed in"Bypass." a)Normally lighted~b)Possibly should be changed to amber color and rewired to light when switch is place in bypass.c)Being added by FDI-~TCHI FEL-2 above switch S123 (Flux Estimator alarm reset switch)White Lighted-Indicates"Flux Estima tor&sdkaea" alarm is sealed i ends Masu4uauce.

a)Normally not lighted b)Possibly should be amber color c)Being added by FDI-TCHI FEL-3 above switch S123 (Flux Estimator alarm reset switch White Lighted-Indicates"Flux Estima tor Failure" alarm is sealed 1 a)Normally not li b)Possibly should amber color c)Being added by FDI-TCHI White light a-bove switch S-114A (LFMG moto breaker 1A con-trol switch)White Lighted-Indicates protective relaying lockout reset for LFM motor breaker 1B a)Normally lighted b)Being added by PED-213 E-2005 White light above switch S114B (LFMG motor breaker'B control switch).White Lighted-Indicates protective relaying lockout reset for LFMG motor breaker 1B a)Normally lighted b)Being added by PED-218-E-2005 White light a-bave switch S121A (RRC-P-pump motor breaker control switch).White Lighted-Indicates protective.a)Normally lighte relaying lockout reset for RRC b)Being added by P P-lA breaker.218-E-2005 Page 23 WNP-2 CONTROL ROOM IND'ICATING LIGHT REVIEW PANEL P602 LIGHT COLOR MEANING REMARKS White light a-bove switch S121B (RRC-P-1B pump motor breaker control switch)White Lighted-Indicates protective relaying lockout reset for RRC-P-1B breaker.a)Normally lighted b)Being added by PED-218-E-2005 Lights (1 each)above Hyd valve isolation to RRC-V-60A and B control switc es White Lighted-Indicates containment isolation signal closed Hyd.isolation valves (Hy-v-17,18, 19,20 A/B)a)Normally not lighted b)To be installed by PED-218-E>>5079.

PED should be modified to delete white lights-they are not needed.Page 24 ANNUNCIATOR SYSTEM DESIGN REVIEW The purpose of this review is to evaluate the design of the WNP-2 Annunciator System against NUREG-0700.

Only those items of a system design nature are included.Those items covered under individual panel HED's or those to be later incorporated on panel enhancement packages were not incorporated herein.This review covers both the Control Room and Remote Shutdown Panels.Concern 1.0 General System Characteristics

1.1 Alarm

Parameter Selection a.Set points or limits for initiating the annunciator warning system should not occur so frequently as to be considered a nuisance, and should be established to give the operator adequate time to respond.U o Present design to be reviewed during startup testing and verified during subsequent plant operation.

No present review required.b.General and multichannel or shared alarms.o An approved"Annunciator System Multiple Input/General Alarm Standard" was prepared for WNP-2 and review results are included in individual panel HED Reports (see Section 6.5).1.2 First-out annunciators should be provided for identifying the initiating event associated with automatic plant shut-downs.Separ ate first-out panels should be provided for the reactor systems and the turbine-generator systems.The panels should be placed directly above the main con-trol stations for the respective systems, and shou!~'on-sist of separate annunciator tiles for each of the auto-matic trip functions.

o A first-out system does not exist.1.3 Auditory signal coding of alarm priority is also"appro-priate" along with color, shape, or symbolic coding.o Present priortization of alarms is by color coding.1.4 Cleared Alarms a.Cleared alarm auditory signals should have a dedica-ted, distinctive, audible signal which should be of finite duration.

o No finite duration circuit exists.b.The visual signal should have a special flash rate equal to either twice or one-half the alert flash rate to allow discrimination.

o Design in compliance.

Uses one-half the alert flash rate, about one (1)flash per second, with equal times on and off.2.0 Auditory Alarm Subsystem 2.1 Signal detection and intensity reviews cannot be reviewed until sound measurements are performed later.2.2 Signal identification should be such that the operator is able to identify the operator work station or the system where the auditory alert signal originates.

Separate aud-itory signals at each work station within the primary op-er ating area are recommended.

o Signal identification for the P601/P602/P603 work area, computer system and the fire panels meet de-sign.However, the P800/P820/P840 work station area and the back vertical panels have one common auditory system.This area does not comply.2.3 Localization coding should be used when the operator work station associated with the alarm is not in the primary area.o The P800/P820/P840 work station area does not have separate auditory location coding but is in common with the back vertical panels..This design does not comply.3.0 Visual Alarm Subsystem 3.1 Lamp replacement should not require the removal of legend tiles or subject the operator to a shock hazard.o Present design complies.3.2 Flash rates should be from three to five flashes per se-cond with approximately equal on and off times.o The present"alert" flash rate is about two cycles per second with 50K on and 50K off times.3.3 In case of flasher failure, the alarm tile should immedi-ately light and burn steady.0 o Present design complies.1 3.4 A"dark" annunicator panel concept should be used.o Present design concept complies.Verification of design wi 11 occur during subsequent plant operation.

3.5 Out-of-Service alarm recognition cues should be designed into the system.o"Loss of 125VDC" annunciators powered from separate AC sources identify overall system power loss for each audible/visual alarm system.Individual panel and tile alarm power loss can be verified by use of the individual panel's"test" control.Present benchboard panel design complies;vertical panel de-sign needs verification.

3.6 Blank

or unused annunciator tiles should not be i llumina-ted (except during testing).o Present design complies.3.7 The operator should be able to read all the annunciator tiles from the position at the work station where the ac-knowledge control is located.o Panels P601, P840, and P820 are not in compliance.

4.0 Operator

Response Subsystem 4.1 Control Functions a.Controls should include a separ ate silence pushbutton for the"alert" auditory system.o Present design does not comply.Separate alert silence controls do not exist.b.It should be possible to silence an auditory alert signal from~an'set of controls in the primary opera-ting area.o Present design does not comply.Only within the tone grouping for panels does this apply.Si-lencing between tone groupings does not exist within the primary operating area.C.Acknowledge should only be possible at the work sta-tion where the alarm originated.

o Present design complies.

d.Reset control should"silence" the audible signal indicating clearance and should extinguish tile il-lumination

'only at work station where the alarm initiated.

o Present design complies.e.A"test" cont~ol should be provided to test the audi-tory signal and flashing illumination of all tiles.o Present design complies.4.2 Control Set Design a.Control sets should have the same arrangement and relative location at differ ent work stations.P601: o P820: Arranged on vertical section of bench-board r ather then horizontal area along panel edge.Located on right side of panel r ather then center.Located on left side of panel rather then center.o P840 Located on right side of panel rather then center, very close to P820 con-trols.Operators have responded er-roneously to the opposite panel con-trols due their closeness.

Fire Panels: Sequence of controls for FCP-1 and FCP-2 is"ACK/Test/Reset" instead of"ACK/Reset/Test" as used throughout the control room.FCP-2 only has"ACK" and"Test" controls, no"Reset" control exist.o P851: System status monitoring panels SD-l, 2, and 3 are being deleted due to RG-1.47 redesign.The new SRV acous-tic monitoring system subpanels will replace SD-1 and SD-2.This leaves the Division I and Division II annunc-iator panels and associated controls in a configuration that places the Division I Controls closer to the Di-vision II Panel than the Division II Controls, and separated by the new acoustic monitoring system subpanels.

o Back Vertical Panels: Control locations are generally below anthropometric limits and are not all consistent in location.B.2 Control coding techniques for easy recognition of controls should be used.Recommended techniques are color, color shading, demarcation, and shape.o Controls are not distinguishable in shape.o Color coding is inconsistent.

24 controls have black pushbuttons with silver collars.61 controls have silver pushbuttons with silver collars.1 control has a silver pushbutton with a yellow collar.The fire control panels use"Red" escut-cheon plates for the"ACK" control rather than black, and the shutdown panel P100 has no escutcheon plates.c.Annunciator design should not allow the operator to defeat the controls.o Problem is minor but probabilty does exist.R ECOMMENOAT ION S 1.0 General S stem Characteristics

1.1 Alarm

Parameter Selection-No action required.1.2 First-Out Annunciation

-The sequence of events printer provides printout of annunciator alarms for reactor, Turbine Generator, and Balance of Plant systems, identifying both the initiating event and the sequence of events associated with plant shutdowns.

Buffer cap-acity, computer speed and printout speed are such that operator in-formation will not be lost, and the response time is adequate for immediate operator access for first-out identification in the pri-mary operating area.To ensure visibility of the initiating event, the printer provides a distinctive coding to sequence of event alarms versus other alarm printouts.

A review is required to ensure all first-out events are included in the sequence of events system.

1.3 Auditory

Signal Coding audible prioritization of alarms is not re-commended.

Operator response on lower priority alarms may become relaxed and additional tones may add to operator confusion.

Opera-tors are to respond to any"alert" alarm equally.Present color prioritization can be visibly seen throughtout the primary operating area on main benchboards.

Audible prioritization would not add to directivity or operator response significently to warrent modification.

1.4 Cleared

Alarms a.Auditory Signal Our ation-To provide duration control for the"Clear" tone, the audio response circuits in each annunciator control card would need to be modified.This would be a major change and possibly schedule impacting.

An alternative, which meets the intent of NUREG-0700, would be to modify the Reset controls.to allow the operator to silence the"Clear" tone from any set of response controls in the primary operating area.Reseting of the flashing"Clear" light would only be allowed at the specific panel.Thus the reset"Clear" circuit would be identical to the acknowledge"Alert" circuit noted in 4.l.b, below.This would provide the operators the added advantage of consistency.

of control function, and control over the audible"Clear" tone.Modify the audio"Clear" portion of the Reset controls accordingly.

b.'Clear Alarm Flash Rate-No action required.Oesign in compliance.

2.0 Auditory

Alarm Subsystem 2.1 Signal Oetection/Intensity

-No action until control room sound studies have been completed.

2.2 Use the Off-Gas Panel P672 alarm audible system for P851 and the back vertical panels, providing a third tone system.This places the main operating work area P800/P820/P840 onto one audible/visual system, and places P851 and all the back panels out of the primary area, and onto one independent system.A general alarm for P672 will need to be incorporated onto P851.2.3 Localization Coding-See Recommendation 2.2, above.3.0 Visual Alarm Subsystem 3.1 Lamp Replacement

-No action required.Oesign in compliance.

3.2 Alert

Flash Rate-No action required.Present flash rate is very close to the minimum guideline and meets the design intent.3.3 Flasher Failure-No action required.Design in compliance.

3.4 Dark Panel Concept-No action required.Design in compliance.

3.5 Out-of-Service Alarms-"Loss of 125VOC" alarms need to be installed on P851 for the back vertical panels when the annuciator system is separated from the primary operating area as noted in Recommendation 2.2, above.Corrective recommendations pending design verification of vertical panel system design.h 3.6 Blank Alarm Tiles-No action required.Design in compliance.

3.7 Tile Readibility

-See Recommendation 4.2.a, below.4.0 Operator Response Subsystem 4.1 Control Functions a.Silence Control-Modifying the present control set design to add separate"Silence" controls for the audible"Alert" signals is not feasible on the main ECCS, RFW, and T-G panels where the feature may most be wanted.Layout changes on these panels would be necessary to provide room, which would affect system configuration control and layout.The addition of the silence control to other panels would provide inconsistency in design and layout, and be of little added value without incorporation on the ECCS, TG, and RFW panels.The annunciator system as is meets the intent of NUREG-0700 design.Inclusion of a silence'control is not recommended.

b.Acknowledge Auditory Function-Modify the Acknowledge Control to silence any control room"Alert" tone (P601/P602/P603, P800/P820/P840, and back vertical panels)from any acknowledge con-trol in the primary operating ar ea.Acknowledging from any back vertical panel should only silence the back vertical panel audible alarm, and not any primary area alarm.The fire system alarm is to remain separate and independent.

c.Illumination Acknowledge

-No action required.Design in compliance.

de Reset Control Functions-Modify design of the audio reset sys-tem per Recommendation 1.4.a, above.e.Test Control Functions-No action required.Design in compliance.

4.2 Control

Set Design a~Arrangement and Location o P601: No horizontal room is available on the front panel edge to provide for location and arrange-ment consistency without affecting panel config-uration and control symmetry.Vertical orienta-tion was selected as the only plausible alterna-tive without significant relocation changes.-31 o P820: Redundant sets were provided due to the length of the panel to improve visibility of the annun-ciator tile from the Acknowledge control.See attached control location drawings.A second test control is not required.Relocate the response controls to the center of the panels horizontally along the panel edge for consistency.

See attached layout drawing.Be-sides improving alarm visibility, controls for P820 and P840 are placed too close together con-fusing operators as to which set of response controls to initiate.Relocation would improve both annunciator tile readability from the ac-knowledge control, and avoid confusion with the P840 controls.o P840: Provide a redundant set of response controls near the RFW systems to incr ease visibility of annunciator tiles, and to increase operator ac-cess and response to RFW alarms from P603 with-out having to leave the P603 area.See attached layout drawings.A second test control is not required.o Fire Panels: Resequence the controls for FCP-1 and FCP-2 to a"ACK/Reset/Test" Sequence.Addition of a"Reset" control to FCP-3 is still pending resolution.

o P851: Contrast and grouping recognition between Divi-sion I and Division II annunciator panels and response controls is pending resolution.

o Back Vertical Panels: Most panels have little available room to relocate the controls within anthropo-metric limits.Relocation would mix them within control areas, reducing their visibility and possibly adding to operator confusion.

Also, as they are, most are consistent in location and height.Relocation would increase the inconsis-tency.No action required.b.Control Coding o Sha e-Use"White" mushroom heads on Acknowledge controls on y on the main benchboards.

Congestion is higher and increased visibility is required on benchboards.

Vertical panel visibility of controls is better, and congestion around annunciator response controls is in general far less than the benchboards.

Mushroom heads not required on vertical panels.-32-0 o Control Color-Use silver pushbuttons except for the 51, black.Locking ring and escutcheon colors will be decided in the enhancement packages.Change out the three black controls on P821 and the one black control on P840 to si 1-ver to provide consistency in these areas.Since the fire panels and P851 form one panel area (row), and all con-trols are consistently black and are about the only con-trols on these panels, no conflicts or confussion is ex-pected.The same rational applys to Panel P100.Leave P100, P851, and the fire panels as they are.o Oemarcation, escutcheon plates, and color shading will be included in the enhancement packages when total color scheme is defined.Oefeatable Controls-Use of mushroom heads noted in Recommen-dation 4.2.b, above, will prevent defeating the most important of the controls (Alert)in the primary operating area.No fur-ther action required.

.o 4 I 43 96 S4 C-l(El=N 00 C 4I53 s9--<~L 4N BuS S~-o 4I73 t:7073 C4I87 4 I 9 3 97 S6 lib 99 S2 I 02.S7 0 ow 00 C4203 IOZ 42 I 3 Io)S5 C4223 e4 SI 2 o Q,,~LIQ 00 C 44 I 3 0 C4 23 8 684 RED Oooo C4433 I6 asa S4 HPcs-C4463 Ib asa SIO 00 C4473 I6 asa S23 BLUE'4503 (~@S I I Qw C 45l 3 8 (o65 S6 00 OQ 0 C4463 C4483 C4523 I6 l8 asa I aso SIZ S3.E.t S20$5l I Oow0 C4733 l6 I mes 00 C4773 X IO RED1 DK CLuE 557 QQw Q Qw 4743 42 S3C C4783 e S5b RED 0~0~0 L I73.J OljO OO C4723 C4763 8 ass Qw 0 C48&: C48l: a S besot Qow(4823 4243 C4 233 C I6 sss S I I 98 SS 4253 LOG S3 each 0.OQ a I5 C4403 C4493 I6 6S6 SI RESET RcK 00 C4 753 C4793 asl S4C hei st~a 0 C4833 6 S HPCS RHR-C PANEL P601 Q 0 QEeoo Q 0 Q ea C56Z.v)~C567Z>>0C57ZZ

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EF VALyeS 0 00 C5933)C5973 l0 esi i 683 SI SI3.t FCS C 0 OOO O(C63C)63I@C6243 CG(i 3 l5 lo lo asI i asI~asI S4A S6A S2A RHR-A PANEL P601 G>>9 Q l3t UE 00.C>>73 (C55&Q t'0)(o6 ()02)-gFw-p ih&50 GLUE, (l05)00')0 0 i5 (So 68 (d 8)0 C5~o I'50 6 Pi'~o)650 68 (7O)CB+zg Ct50 68 (Vl)RcK p~seg Rcw-&50~I'-is BLuE,@S (lO+)BLUE BLUE 6~0 85 Qw Qa 0 0(604@QACsssg Css93(I 00 Cs46 3 43T R-lB (@80 GC-l 8 (l4)79 Cssog Tg l8 64Z 85 (24)74)Cs47 3 Css(3 qaqp 43QP l-lo 2-lB (6)72 (l 6)75 QA Qa Css20 642 85 Cs4()g (Zs)(3g Cssag 642 85 430T TR-l B (la)l8)00 Cs4s g Css(3'ss 73 43P E-lB (E6)7s Csoils 642 85 00 CS583l'5oJ (8 (zo)00 L Co5 5'3 00 C'5543$50{ao (fit<)C(63(()Csa4$(63()Cs6s 3 639 6B-(zz)4 A A A 0 C 50&d Cs>>3 a%0 s8 (7b)00 GREEN 650 s6 (75)00 Cs 703 aSO 68 89 00 Cs7(7~6EO 65 (9l)00 C>>-.J ggo 68 (7~)00 Cs 75/ceo 68 (7)GREE (608)G R Cs 7+/A RFW SYSTF~6 PANEL Psqo Ot=R Bbp 46'6)y5 00 0 0 SlO Q 0((0l)0 soog$505$Sll J OE&(~)TQ-ALP" I (7)TG THCrl (~)51:00 00 CSO I 3 EHP-IA (I)Qw t SOZ3 EHP-1B (?)44 0 0;t:512-3 0 0('gj5j Qsi3 J 0 0(~il)t si43 86/'FT (ao)86/'R-V-.ASO (&el)~~49 TURBINE L497 J L498$Q Q+Q so3$Ls l7g EOP 00;I so4$SYNE H L6l6+6 l3)Lsz l Q(608)L5293 00 00 00 L6l l (6H)t 522$(609)$530$Lsis J, 596 (61 ss-v-Esssl~~

0'0 QO 00 Qg2,OQ'$528$L536 59&~~..59&53~>~5g (iPO~(10?)~(103)-V" GSJD-V-'COND-V-&09A.609B..609C l83.COND-TCY-X (12)Cssag 6SI CVS (42)4g 00 00 00 00 MSR-A 00 00 Ls~Q~73 (l028)59&gp (17)85-V-ZIA MG-V!OIA 00 00'sca%L 9~ss.65-V-IA N5-Y-7OA 00 (j C)5591.)9b~~594 I (zz)I'(,g)P.)-V-2A M5-V-l02A+see 598~~59&@~'gp)l (gg)M5-V-l08A 65-V-Z2A OQ 00 I S4O3."CS443 59b ry 59b 5$~(3e),~(si)lit S-V" BS-V-108 8-22 B Section 6.3-Panel Confi uration Reviews Panel configuration reviews cover specifically the human factor areas of Control-Display Integration, Panel Layout, and Controls.Other areas of human factor concerns, such as, anthropometrics, mim-icing, and demarcation, hierar chy labeling, color coding, etc., were also integrated in with the panel layout design reviews.This was to ensure that all design aspects were covered in the review and that recommended correction configuration changes would later allow for the addition of panel enhancements.

Reviews were performed on a panel and system basis.Each system was reviewed for operability, layout and integration with supporting systems and systems it supports.Corrective recommendations and reports were prepared for each panel noted on Table 6.3, below.In addition, proposed reg'ulatory, engineering, and operational changes were integrated into the reviews.These specifically included RG-1.47, RG-1.97, SPDS, and Emergency Procedure requirements.

Prior to finalizing panel configuration design on the primary area benchboards, panel arrangement drawing were prepared to reflect the proposed layout design, incorporating additions of potential mimic-ing, demarcation, and label grouping changes.Final configuration, including mimicing and demarcation, were mocked on the the ECCS Panel P601 in the WNP-2 Control Room to provide perspective of the recommended corrective actions and potential enhancement capabilities.

To date, all Panel Configuration Reviews have been completed.

Ap-pendix A contains a typical documentation package for Control Room Panel Configuration Reviews.The typical package includes a Review Report, HED Report and Task Force and Project Directive transmittals for implementation.

Further Configuration Reviews will be documen-tated in the WNP-2 final control r oom report.

TABLE 6.3 PANEL CONFIGURATION REVIEW LISTING Panel A.Operating Panels-Primary Area P 601 P602 P603 P800 P820 P840 Reactor Core Cooling Systems (ECCS)Reactor Water Cleanup and Recirculation Reactor Console Electrical Generation and Distribution Main Turbine Systems Reactor Feedwater and Miscellaneous Systems B.Operation Panels-Outside Primary Area P672 P811 P812 P813 P814 P821 P824 P825 P826'827 P832 Off-Gas System SGT and H2 Recombiner; Division II Reactor Building HEV Containment Vent and Purge Containment Monitoring System Main Steam Leakage Controls Cooling Tower Controls RCC and SW Systems Control Room HVAC SGT and H2 Recombiner; Division I RFW Heaters;Vents and Drains C.Operating Panels-Remote Shutdown Area P001 RCIC and RHR-B Systems P100 SW-B System SECTION 6.4 CONTROL ROON ENHANCBlENT REYIEHS The purpose of the Control Room Enhancement Reviews is to identify areas of human factor visual enhancements, prepare appropriate standards for consistent application, and recommend appropriate enhancing or corrections on a panel by panel basis.MNP-2 Standards are presently under preparation and scheduled for approval in ear ly 1982.Enhancement reviews will include application of such areas as: o Abbreviations (standard approved October 1981)o ilimicing and Demarcation o~Color Coding and Color Padding o Legend Plate Structure and Content o Control Switch and Handle Application o Range and Setpoint Identification o Switch Escutcheons o Indicator/Recorder Scale Standards o Recorder Chart Paper Application o Unique Identification of Post Accident Monitoring Instrumentation Panel enhancement reviews are scheduled to start in February 1982 and complete in December 1982.Observations noted during the Preliminary Assessment Report of December 1980 are: 1.0 PANEL LAYOUT AND DESIGN 1.1 Demarcation and Mimics 1.1.1 Demarcation lines do not exit on any panel.Panels have poor contrast between systems and subsystems controls, and their display/control relationship.

Preliminary reviews note that application of system separation lines will not be a problem.But application to the subsystem level may require some relocations of displays/controls and/or color coding and/or better legend plates.This was reviewed in conjunction with the panel configuration reviews noted in Section 6.3.0

1.1.2 Mimic

Oisplays 2.Panel P851 is heavily conjested hindering operator status review.No summary indication available to operator to identify status of valve isolations.

Yellow is used for 4.16 kv power on P601 and 480 volt power on P800.Blue is used for 4.16 kv power on Panel P800.3.4.Color legend identification plates are not located on mimic panels for operator reference.

Mimics are used only on seven panels.6.P840 and P601 do not have arrows indicating direction of flow or energization.

For the few arrows that are'sed, 3 are backwards.

P813 containment vent and purge ventilation mimic is crowded, incomplete and a small section has its ar-rows backwards.

7.Minor mimic additions and relocations are needed on P820 and P800 to improve display information and avoid conjestion.

8.9.Color coding of P800 needs to be changed from a"voltage level" concept to a"source-distribution" concept which provides more useful information to the operator.Bus Legend plates on P800 are not located on or in close enough proximity to the mimic lines for easy of Bus identification.

In most cases they look more like switch legend plates due to their close location to the switches.10.Panel P832 mimic is not accurate.1.2.1.An overall color coding r eview was not completed.

How-ever.the following was noted: Ho overall plant color standard exists for the selec-ted use of demarcation lines, alarm prioritization, indicating lights, labels, legend plates, graphic displays, mimics, tags, etc.2.The primary area of concern noted-to-date is in the use of indicating light colors to provide consistent information to the operator.See"Indicating Lights", Section 6.2.4 of this report.-41 E 1.3 Legend Plates, Labels, and Escutcheons 1.3.1 Use of technical terminology and sistently applied.1.REVAB is still used on P601 abbreviations is not con-and P602.2.CRD on P603 flow indicator is written"CONT.ROD DR." 3.Some pump and valve switches are identified by motor number, while others are identified by the pump or valve number.4~I Controls and Displays are identified on some panels by their GE equipment piece number (e.g.P601, P602, P603)while other panels identify them by their Burns 8 Roe equipment piece number (e.g.P800, P820, P840).1.3.2 5.Motor Control Center notation to define power source is not noted on the legend plates.Operators have started placing labeling tape at controls.Use of standardized abbreviations and there application needs improvement.

209 different terms are abbreviated.

Most are easily identifiable to the operator, and some identifiable due to their panel association.

Areas of concern are: 43 terms (20K)have more than one'bbreviation.

Of these;32 have two methods of abbreviations 6 have three methods of abbreviations 3 have four methods of abbreviations 1 has seven methods of abbreviations Thi s i s 58 extra abbrev i at ions that may not be need-ed, and in some cases cause confusion due to conflic-ting usage.2.Application of abbreviations in some cases was unwar-ranted and increases operator confusion.

This was especially notable where adjacent controls of repetitive function were labeled differently; one abbreviated, the other spell'ed out or both abbrevia-ted differently.

3.Conflicting abbreviations exist which reduce clarity of description.

a.Containment is highly used throughout the con-trol room and has seven different abbrevia-tions.

b."Neut" is used for neutral and neutron.c.Neutral and normal terms and abbreviations are used interchangeably, and neither provides defi-nite information to the operator.d."STG" is used for stage and storage.e."FL" is used for floor and flow.f."CL" is used for coil and cooiling coil, whereas"CLG" is used for cooling, and"CLG CC" used for cooling coil.g."Cond" is used for condensate and condenser.

h."OR" is used for drain and drive.Application of legend plates were generally found to be acceptable.

1.Legend plates are located consistently above switches and below controllers, lights and indicating devices.2.Legend plates were'f consistent type, size and color.Size length varied due to its application.

3.Size and style of lettering was consistent.

Legend plates used on relay or test panels are not suffic-iently worded with respect to function or input signal.E.g., use of relay piece numbers do not adequately provide the operator information about the relay's function or relationship to plant systems.System and group label ing, and other general type 1 abel s, are not consistently applied, do not always have contrast, and in some cases are difficult to distinguish and dis-tracts from process legend plates.System legend plates of a light color and large size are used on P601, P602 and P603.Those are distinctive and help the operator to foc-us on systems and controls.System legend plates on P840, P820, P800 are colored black, the same as process legend plates, and are difficult to spot.Summary type labeling is ineffectively used in the control room as an operator aid.Panel Identification Labeling was found to be inconsistent.

l.Yellow panel legend plates are intermixed with black panel legend plates without apparent pur pose or con-sistent application.

2.3.Yellow plates with black lettering are about 505 larger than the labels using black plates with white lettering.

Size of legend plates and lettering is fairly uni-form, except for: a.P634 panel label and print is about 5 times larger than any other.b.P825 label print is excessively small, conjested and difficult to read.4.Inconsistent terminology is used to identify the ver-tical panels (Board.Board"H", G-II without the term board or panel, and combinations of terms like H13-P851 (s).a.The use of conflicting terminology is confusing from a training and operating view point.b.Abbreviations are used unnecessarily and incon-sistently with the space available (VB, vert BD, vert board).5.Front main panels do not have panel legend plates in their design.6.RCC is used twice in P825's label'without need.2.0 INSTRUMENTATION AND HARDWARE 2.1 Manual and Automatic Controllers 2.1.1 2.1.2 2.1.3'With a few exceptions, green band color markings are norm-ally used to aid the operator to spot deviations.

How-ever, the green bands are located on the covers and not on the scales.This increases parallax.Correlating scales to process units and to backup indica-tors was found inconsistent.

Several controller scales were noted as 0-100K for level rather than actual level.guite a few controllers differed from their backup indica-tors by multiples of 10 to 1000.One controller on P840 had taped on makeshift scales.'ording of legend plates was inconsistent.

Some identi-fied their controllers by equipment number, most by de-scription.

some without identifying the function (flow, temp., pressure).

Wording differences, in a few cases, between the controller and backup indicators made it dif-ficult to quickly verify response.44 2.1.4 I 2.2 Recorders Units of measurement were not noted on some controller scales or legend plates.Flow could be CFt<, gpm or lbs.per hour: temperature could be oF or oC;etc.This is particularly bad for controllers without backup indicators.

2.2.1 Color

Review 1.Red is consistently used for the upper scale on dual pen recorders.

2.Red is usually used to designate the high range on dual pen recorders.

Exc ptions are: a.Panel"J" where low range is red.b.Panels"Kl" and"KII" recombiner readings for gas and recycle flows, low range is red.3.Red is usually used to designate the first of two items;ex: Loop A vs.Loop B.Exceptions are: a.P602, Recirc Flow/Suc.Temp.Recorders (2).Loop A is red on one recorder and Loop B is red on the other.Side by side proximity creates confusion.

2.2.2 Recording

Speed Review 1.lletwell level and pressure are single speed at 4"/hr.(Panel P814).Metwell temperature and drywell para-meters are monitored at 2"/hr.2.2.3 2.Flux recorders and computer trend recorders are man-ual switchable from 1"/hr to 60"/hr, and 6"/hr to 60"/hr respectively (P602, P603 and P840).The re-corderss have to be slid out of their cases to reach the speed control switch.Chart Paper and Recorder Scales 1.Of the 85 recorders in the Control Room, 30 had no paper installed as yet.2.Of those 55 installed, 21 had scales different than the scales of the recorder or had single scale paper for dual scale recorders.

3.Of the 85 recorders, 43 did not have the units of process measurement either noted or readily visible on the recorder scales, nor their multiplication fac-tors;eg.CFN, GPM, oF, x100, xl000, etc.

4.Of the 51 dual pen recorders, 24 had no or partial designation as to the parameters being recorded.In a few cases, equipment piece numbers were given rath-er than the parameters.

Eg., post-Accident Monitor-ing Recorder, parameters measured are"Press XMTR B22-N051A" and"LVL XMTR B22-N026A." 5.Several scales are noted as 0-100.Without the para-meter or units of measurement being noted, it is dif-ficult to establish if the scales are actually the process variable or simply 0-100 percent.Several have already been temporarily marked to actual pro-cess units.a.Panel P824, cooling tower flow is 0-40,000 gpm, not 0-100K.b.P840, blowdown flow recorder was 0-100K and a makeshifted scale now reads 0-7500 gpm.c.There are 12 other recorders having 0-100 scales that may need to have scales changed out.2.2.4 Miscellaneous 1." f" is used throughout the control room except for the scales on P820, transformer temperature recorder, which read in oC.2.No color coding or markings were noted to indicate: a.Normal or abnormal range of operation.

b.System trip or alarm settings.3.Many recorders have doors with white strips on both~sides.The color is sharp and eye catching, and hin-ders quick focusing on the recorder chart.4.Multipoint recorder on P600 has foggy glass making readability of the print out very difficult.

2.3 Indicators

(Meters)2.3.1 Marking and Scale 1.Process units are labeled clearly on scale faces, use fairly large print and easily readable.Exception noted: a.P601;RHR AKB"Cond." indicators has no process units identified.

2.Abbreviations were kept to a minimum and are consid-ered acceptable.

3.Color coding or other markings are not used to indi-cate normal or abnormal ranges of operation or as indicators of system limits or trips.4.Scales are generally unconjested, have good contrast, are numbered in either whole units or easily divis-ible units of 1, 2, or 5.Noted exceptions are: a.P603;identical steam flow and feedwater flow scales (6)are heavily conjested making it dif-ficult to read and extrapolate, and one of the steam flow,scale's length is different than the other three.b.P840;CW inlet plenum indicators (2)and record-er (1)have uneven scale values making it diffi-cult to read and extrapolate.

5.Indicators are marked in actual process units and percentage is generally used for valve position or air/moisture content.Noted exceptions are: a.P601;RHR HX shell level (2)scaled from 0-10(5, and not actual level.b.P617;jet pump flow indicators (20)are 0-100K.Legend Plates 1.Legend plates should provide a description of the function being monitored (RHR A Shell Level), state the parameter being monitored (Level)and/or state the unit of measurement (feet).P601 legend plates are considered the poorest in this regard and should be improved.2.Some inconsistency in labeling was noted.Some panel labels use equipment piece number, some use descrip-tion, a few are intermixed.

3.Use of similar descriptions on legend plates of re-lated pieces of equipment (Pump A, 8&C)was gener-ally found to be very good.A few exceptions were noted on Panels P812, P603, P840 and P820.4.Group labeling of indicators needs improvement.

Use of individual legend plates for indicators in clus-tered groups adds excess wording, unnecessarily use of abbreviations due to small available space, cause excess redundancy, panel conjestion and is more dif-ficult for the operator to focus on and read.Com-bining several legend plates into one (e.g.P603 Feedwater Indicators) helps the operator to quickly..~identify an individual indicator and its relationship to others.Also, improved hierarchy labeling would help considerably.

P840 and P820 are prime examples of this problem.2.4 Switches-Primary Operating Area 2.4.1 Pushbuttons l.Emergency trip buttons on P601, P602 and P603 are generally consistent in application.

They are raised, shielded to prevent inadvertent operation, colored red for visibility and have arm/disarmed features.Several concerns noted are: a~b.Emergency trips for the Diesel Generators (2), RFW pumps (2), T.G.(2), and Generator Unit (2)on P840, P820 and P800 are incon-sistent (type switch, color, etc.)with the above and also between, themselves.

They lack visibility and contrast with surround-ing controls.RCIC turbine and manual steam isolation trips on P601 have the same problem as"a" above.2.4.2 2.Pushbutton"Containment N2 Backup Valve CIV-V-39B" is mislabled.

The control is used for testing the Digital Electric-Hydraulic pumps.SBM Switches 1.The use of SBM switches with colored flags are'ot consistent in application.

No policy or criteria was located to define when a"flag" SBM control head should be used.In general bus.control switches have"flags".Noted inconsis-tencies are: a.Bus controls on HPCS P601 do not use SBM's with flags, while bus controls on P800 do.b.HPCS diesel control switch on P601 does not use a flag, while diesel control switches on P800 do.

2.I SBM switches are used for control of all pumps except for the auxiliary lube oil pumps, water leg pumps and vapor extractor oil reservoir pumps.These used CR 2940 switches.Also, some SBM switches are used for valve control, where normally CR 2940 switches are used.3.SBM switches for synchronizing OG busses 01 and II'2 on P800 use special handles.Yet synchroni-zing switches for HPCS and the normal bus con-trols on P601 and P800 use regular J-handles.

Special handles are applied inconsistently.

CR 2940 Switches l.Black colored direction arrows located on top of the switch operators have little visibility and lack contrast.Escutcheons 1.Lettering size and font on SBM switches vary.Some are bold and large and some extremely small and unreadable.

Added on position markers do not follow lettering size or font pattern of existing markings.2.Escutcheon nomenclature is inconsistently ap-plied and, in some cases, misleading.

a."Neutral" is used on P820 in place of"Normal".b."Normal" is sometimes stated in full and sometimes abbreviated"Nor" or"Norm".c."START, ON, and RUN" are used interchange-ably for pumps and motors.d."CLOSE and OFF" or"STOP and OFF" are used interchangeably for valves and pumps.e.No designation is noted on escutcheons, legend plates, or by type of switch, as to whether switches are jog control, seal-in, or spring return to center.f.Escutcheon markings on CRD pump switch, P601, notes no center position, yet the SBM is a spring return to center.

g.Ecutcheon markings on RFM main oil pump switch.P840, notes no center position, yet the SBM has a stop with no spring return.0 h."OFF and CLOSE" are sometim s used in the center escutcheon position, contrary to the normal"LEFT" position.i.~NORMA and AUTO" are normally in the cen-ter switch position, but in a few cases, are on the right.3.TSW-P-1A 5 B, P840, escutcheons reads"Normal Stop-Auto Stop"."Normal Stop" is unclear and confusing.

and"Stop" should be"Start".4.Oiesel control (starting) switches on P800 are a SBM flag type labeled Trip/Reset rather than Start/Stop.

2.4.5 Miscellaneous

l.IRM Range Selection Switches on P603 have thin color coded lines, red and black, for referen-cing the switch position to the appropriate colored scale on the recorders.

The switches color coding lacks visibility and contrast.2.5 Switches-Vertical Panels 2.5.1 Pushbuttons 2.5.2 In general,"Test" pushbuttons are black, while an-nunciator and other"reset" pushbuttons are silver colored.This is not consistent with the main panels where both reset and test pushbuttons are silver.SBM Switches Use of SBM switches with and without flags in not consistently applied.1.Panel P812-10 SBM switches for supply and ex-haust fans use"flags" while three SBM switches for fans do not have them.Fans on P811, P813, P826, P827 Vertical Panels use SBM switches without flags.2.Panel P813 has four (4)SBM switches with flags for valve control and one (1)SBM without a flag for valve control.0 CR 2940 Switches Two different sizes of CR 2940 operators are used on Panels P811, P825, and P827.Escutcheons 1."Neutral" is used on some SBM switches in place of"normal".2.Some SBM switches have added-on center position markers which are small and hard to read.Mi seel 1 aneous l.Motor Control Center notation to define power source is not noted on legend plates.Operators have started applying labeling tape above switches.2.Color coding for special switches on Panels P813, P824, and P832 are generally consistent in color coding (green/closed, red/open).

Excep-tions are: a.Panel P832-Switch legend on upper right grouping of switches.third row, second column, have there"AOTO" and"Hi Level" colors reversed.b.CSP-V-6 on Panel P813 is green to open instead of red.3.Special switches on Panel P832 do not have a positive"Auto" position stop.The operator could turn the switch towards auto, but not be engaged in auto.4.Panel P811 and P827 air heater controls and in-dicators are inconsistent in nomenclature and location.Located above SGT-EHC-lA-1 switch are coil, trip and temperature control indicators specified for lA-2, not 1A-1.SGT-EHC-1A-2 re-lated indicators are noted as lA-l, not 1A-2 as they should be.Equipment identification is reversed.The same applies to SGT-EHC-1B-1 and 1B-2.-51

3.0 ANNUNCIATOR

SYSTEM 3.1~Groupin.3.1.1 Contrast within annunciator panels is poor.Use of de-marcation lines to contras.groups of alarms within a panel and/or minor regrouping would aid the operator in quickly focusing on o.scanning systems or similar activities.

3.2 Legend

Plates and Windows 3.2.1 Panel P813 uses HI and HII in the general annunciator le-gend plates.This is confusing and inconsistent with other panel legend plates.They should specify Oivision I and Oivision II.3.2.2 Abbreviations need to be upgraded to be consistent.

Sec-tion 6.5 of this report will handle window engraving concerns.3.2.'3 Window legends do not specify trip points or parameters.

3.3 Display

and Layout 3.3.1 3.3~2 Panel alarm numbering is in a row/column sequence using a numeric/numeric scheme.Annunciator panels are not marked for identification.

Plant Operations intends to attach Annunciator Response Booklets, for each annunciator panel, to the associated control panel's front face for availability and ease of'eference.

3.3.3 Annunciator

circuit pushbuttons lack contrast and visi-bility amid other panel controls.Operators have bracket-ed them with colored tape.

SECTION 6.5 CONTROL ROOM ANNUNCiATOR PANEL REVIEWS The purpose of this review is to evaluate individual annunciator tiles, panel by panel..for grouping.color prioritization; window wording, general or mul-tiple actuation input concerns, and the need for adding or deleting annuncia-tors.The review covers all the annunciators in the Control Room and the Re-mote Shutdown Panels.In addition, the proposed RG-1.47 changes have been factored in.1.Annunciator Grouping-annunciator tiles are reviewed within each annun-ciator panel for grouping by major system or function, and for location relative to respective controls, displays, and operator response requirements.

2.Annunciator Window (Tile)Color Priortization

-A"WNP-2 Control Room Annunciator Window Color Standard" was prepared and approved by the Task Force in November 1981.Present design has only NSSS benchboards P601, P602, and P603 prioritized by color.The Task Force approach was to pre-pare a uniform WNP-2 standard and apply it to all annunciator panels under the scope of this review.3.Annunciator Window Wording-Each annunciator tile is being traced to its orginating source to verify its function and determine the informational requirements for the operator.Besides wording and clarification changes, window tiles are reviewed against the"WNP-2 Standard List of Acronyms and Abbreviations for Control Room Labels and Legend Plates".The standard was prepared and approved by the Task Force in October 1981.4.General/Multiple Input Annunciators

-A"WNP-2 Annunciator System Mul-tiple Input Alarm Standard" was prepared and approved by the Task Force in November 1981.The WNP-2 annunciator system does not have reflash circuitry installed.

The standard provides guidance for determining the acceptability of annunciator alarms with mutiple inputs, and acceptable methods of corrective actions to resolve multiple input concerns.5.Addition and/or Oeletion of Annunciators

-This area of review covers RG-1.47 integration with its resulting additions and/or deletions of alarms;relocation of tiles between control room benchboards and vertical panels, or to remote local panels outside the control room: identifying outstanding design changes;and other additions, deletions, or circuit modifications noted by the Task Force.There are over 1500 annunciator alarms in the HNP-2 Control Room, with about 1200 in the primary operating area.These are located on 47 annunciator panels.The Task Force has completed Review Reports on 44 of the annunciator panels, and has prepared HED Reports.which include corrective recommenda-tions, on 40 of these panels.Task Force reviews are scheduled to be com-pleted in January 1982.

Appendix"B" contains a typical documentation package for Control Room Annunc-iator Panel Reviews.The package includes a Review Report and a HED Report.Project directives for implementation are not included as in the typical docu-mentation package of Appendix"A".Project directives on annunciator panel changes ar scheduled to be issued by end of January 1982.Further Annuncia-tor Panel Reviews will be documented in the MNP-2 final control room report.0 APPENDIX A TYPICAL PANEL CONFIGURATION REVIEW DOCUMENTATION PACKAGE PANEL P602 Review Report HED Report Pr ioritization Criteria Letters of Direction~Pa e A-1 A-5 A-6 A-14

CONTROL ROOM PANEL LAYOUT DESIGN REVIEW PANEL P602 RWCU and RRC Control Panel Concern Panel P602 provides controls for the Reactor Water Cleanup (RWCU)and Reactor Recirculation Control (RRC)systems, with several miscellaneous groupings of Main Steam Line (MSL)drain valves, radwaste equipment drains, and Reactor Feedwater (RFW)isolation valves.Except for the lack of contrast between systems or groups of controls, which in general.applies to all the control room panels.specific concerns noted are: 1.The RFW isolation valves are not grouped with the feedwater system con-trols on P840, and are essenti'al equipment whose controls are located on a non-essential panel.No functional need exists for the controls on P602.2.The MSL drain grouping of controls can be arranged into four basic flow paths or control groupings; RPV head vent.MSL drains, and drains from main steam isolation valves MS-V-28 (A, B.C, D)and from MS-V-22 (A, B, C.D).There is a lack of contrast between the four groups, and some controls are not arranged with their respective drain groups or consis-tent in operating sequence.Specific conserns noted are: a)MD-V-73 drain control is not grouped with its respective bypass valve or operationally sequenced with the other main steam line drain controls.and is mixed with the MS-V-28 isolation valve drain controls.b)MD-V-60 drain control for isolation valves MS-V-28 (A, B, C, D)is not grouped with the respective bypass valve, and is mixed with the main steam line drain controls.c)MS-V-21 and MS-V-156 drain controls for isolation valves MS-V-22 (A, B.C, D)are not consistent in arrangement with the other drain groups.This section of P602 has the drain controls arranged in a horizontal sequence, except for these two controls, which are in a vertical sequence.'.

The RWCU system lack visibility as to flow path or operating sequence.The arrangement requires increased operator knowledge and awareness of the system flow path to function.Specific concerns noted are: a)The RPV vessel reject controller is separated from its respective valve controls, and should be grouped together to facilitate operation.

-A-1 Rev.1, 12/8/81

b)The RWCU system controls are not arranged to facilitate ease of ope-ration.The two system bypass valve controls are not grouped to-gether, the system suction controls are reverse of normal sequence convention (BA rather than AB)and control operating sequence jumps both vertically and horizontally rather than a smooth sequence from left to right.c)RWCU-V-40 is an essential control valve whose control is located on P602, a non-essential panel.Per engineering, RWCU-V-40 should be moved off of P602.d)The two RWCU system conductivity recorders are reverse of normal convention (outlet before inlet).4.RRC system reviews noted the following concerns: a)RRC Loop A and B isolation valve controls blend too well into the panel arrangement.

Contrast is needed to improve their visibility for access and to prevent inadvertent operation.

b)RRC two pen recorders R650 and R614 are inconsistent in use of pen color code.R650 has Loop A and B temperatures as red and black, respectively, while R614 has Loop A and B flows as black and red, respectively.

Color coding is not consistent.

c)A design change (FDI-TCHI) has located controls and indicating lamps for the flux discriminator master controller (located on P603)with RRC Loop B displays on P602.This needs to be reviewed with respect to system grouping and demarcation application before installation.

5.d)Flow control valves RRC-V-60 (A, B)are hydraulically operated.PED 218-E-5079 specifies that the hydraulic system isolation valve con-trols HY-V-17, 18, 19, 20 (A/B)be located on P602.Per engineer-ing, the PED must be changed to relocate the essential hydraulic isolation valve controls from P602, which is a"non-essential" panel.A new location is required.I Two CRT's will be used for the Safety Parameter Display System (SPDS).A location is required for the CRT's.Recommendations 1.Relocate RFW-V-32 (A, B)and RFW-V-65 (A, B)to Panel P840.The four feedwater controls are for manually isolating the RFW system.Since these are not automatic isolation valves, placing them on P601 NS4 area would be inconsistent with the present controls at the NS4 area.The RFW controls were therefore, relocated to P840 and grouped with the other RFW system controls.See P840 for details.-A-2-Rev.1, 12/8/81

b)The RWCU system controls are not arranged to facilitate ease of ope-ration.The two system bypass valve controls are not grouped to-gether, the system suction controls are reverse of normal sequence convention (BA rather than AB)and control operating sequence jumps both vertically and horizontally rather than a smooth sequence from left to right.c)RWCU-Y-40 is an essential control valve whose control is located on P602.a non-essential panel.Per engineering, RWCU-V-40 should be moved off of P602.d)The two RWCU system conductivity recorders are reverse of normal convention (outlet before inlet).4.RRC system reviews noted the following concerns: a)RRC Loop A and B isolation valve controls blend too well into the panel arrangement.

Contrast is needed to improve their visibility for access and to prevent inadvertent operation.

b)c)RRC two pen recorders R650 and R614 are inconsistent in use of pen color code.,R650 has Loop A and B temperatures as red and black, respectively, while R614 has Loop A and B flows as black and red, respectively.

Color coding is not consistent.

A design change (FDI-TCHI) has located controls and indicating lamps for the flux discriminator master controller (located on P603)with RRC Loop B displays on P602.This needs to be reviewed with respect to sys-tern grouping and demarcation application before installation.

d)Flow control valves RRC-V-60 (A, B)are hydraulically operated.PED 218-E-5079 specifies that the hydraulic system isolation valve con-trols HYD-V-17, 18, 19, 20 (A/B)be located on P602.Per engineer-ing, the PED must be changed to relocate the essential hydraulic isolation valve controls from P602, which is a"non-essential" panel.A new location is required.5.Two CRT's will be used for the Safety Parameter Display System (SPDS).A location is required for the CRT's.Recommendations 1.Relocate RFW-V-32 (A, B)and RFW-Y-65 (A, B)to Panel P840.The four feedwater controls are for manually isolating the RFW system.Since these are not automatic isolation valves, placing them on P601 NS4 area would be inconsistent with the present controls at the NS4 area.The RFW controls were therefore, relocated to P840 and grouped with the other RFW system controls.See P840 for details.-A-2-Rev.1, 12/8/81

.~'

2.Rearrange the NSL drain controls to improve grouping and visibility of the four groups of drain controls.The air operated valve controls were located to the right of their respective bypass controls for consistency of arrangement, and demarcation lines applied to provide contrast.3.Rearrange the RWCU system.a)The RPV vessel reject controls were grouped together in an opera-tional sequence, and the RWCU system flow path ar ranged in a smooth operating sequence from left to right.With the addition of mimi-cing demarcation lines and a system flow diagram legend plate, oper-abilityy of the system is significantly enhanced.b)Retain the control for RMCU-V-40 on P602.On review of RWCU-V-40 isolation valve control, a more appropriate operational location could not be identified than with the RWCU system on P602.Upgrade Panel P602 to an"essential" panel.4.The RRC system arrangement was found to be satisfactorily arranged and grouped by Loop A and Loop B.The concerns noted earlier were resolved as follows: a)Install mimicing on RRC Loop A and B per the configuration drawing.The added mimicing provides contrast and visibility as to the rela-tionship between the isolation valves, flow control valve control-ler, and pump controls.b)tlodify recorders R650 and R614 such that the red pen in each record-er is used for Loop A readout.This is consistent with other two pen recorders.

c)Relocate controls S122 and S123, and lamps FEL-l, 2, and 3 per the configuration drawing.This removes the controls from the RRC Loop B area of the panel, placing them in a general area close to its associated master flux controller on P603.d)Retain the HYD-V-17, 18, 19, 20 (A/B)hydraulic line isolation valve controls on Panel P602.Lockup of the RRC loop flow control valves is required under certain operational conditions.

Access near the flow valve controllers is needed.The hydraulic isolation valves were therefore kept on P602.Upgrade Panel P602 to an"essential" panel.5.Locate the two SPDS CRT's on P601 and P602.Tentative locations have been identified and r served for the CRT's.The planned location on P602 appears to provide ready access and clear visibility to the operator from the feedwater and reactivity control area of the control room.final layout approval is pending engineering design, hardware selection and operational review of the Emergency Procedures.

~-A-3-Rev.1, 12/8/81 EQUIPMENT AFFECTED BY RECOMMENDATIONS RWCU AND RRC PANEL.-P602 A.RFW System 1.Remove to Panel P840: RFW-V-32A RFW-V-32B B.Main Steam Line Drain System RFW-V-65A RFW-V-65B 1.Rearrange per configuration drawing: C.RWCU System MS-V-20 MS-V-21 MS-V-69 MS-V-156 MS-V-71 MS-V-72 MS-V-73 1.Rearrange per configu.ation drawing: D.RRC System RWCU-V-31 RWCU-V-34 RWCU-V-lA RWCU-V-1B RWCU-V-40 RWCU-V-42 RWCU-V-44 RWCU-V-100 RWCU-V-104 RWCU-V-106 1.Modify recorders R614 and R650 such that the red pens are used for Loop A, and black pens for Loop B.2.Modify FDI-TCHI rearrangement per configu.ation drawing: B35-S122 B35-S123 FEL-1 FEL-2 FEL-3 3.Change PED 218-E-5079 to locate HY-V-17, 18, 19, 20 (A/B)controls on Panel P602 per recommendations.

E.SPDS l.Install SPDS CRT per configuration drawing.-A-4-Rev.1, 12/8/81

~~~~~'~~~~~~~~~I~~~I~+I~~~~~~~I~~~~~~~~~~~~I~~~I~~

~o Note 1)-~Cate ot HED Report No.Page 2 of Category Safety Related, Minimum Opportunity to Correct Error Category II-Safety Related, Some Opportunity to Correct Error Category III-Reliability Related, Minimum Opportunity to Correct Error Category IV-Reliability Related, Some Opportunity to Correct Error Category V-No Impact on Safety or Reliability In Terms of Need: Category 1-To enhance safe operation, the change should be made.~Remove or mitigate discrepancy

~Provide error feedback to the operator~Increase time to respond to error Category 2'-To enhance safe operation, the change should be made.Category 3-To enhance reliable operation, the change may be desirable.

~Remove or mitigate discrepancy

~Provide error feedback to the operator~Increase time to respond to error Category 4-To enhance reliable operation, the change may be desirable.

Category 5-Change may improve operations.

a.High b.Medium c.Minimal Risk Assignment Based on: Guidance in draft NUREG-1580, 0659 6 0700.NRC audits of other control rooms.BWR Owner's Group decisions.

Note 3)Schedule to Com lete-1.Prior to fuel load 2.After fuel load 3.Never-A s 0 P PANEL P602 WNP-2 HUMAN ENGINEERING DISCREPANCY REPORT RWCU (4.1)REPORT NO.017 Page I of Z DATE~~81 DESCRIPTION OP HUMAN ENGINEERING DISCREPANCY

~s~'..PROPOSED CHANGE;CATECORY'1)LIS~RIS SCHEDULE TO: (2)'OMPLETE(3)MAN-HOUR REQUIRED REMARKS I CO 1)The RWCU systen lacks visibility as to flow path or operating sequenc Specific concerns ares a)The RPV vessel re)ect control-ler is separated froa its respective valve controls.b)The RMCU system controls are not arranged to facilitate ease of operation.

The two systen bypass value controls are uot grouped to-gether, the systen suction controls are reverse of norual convention (Bh rather than AB)aud control operatin sequence gunps both vertically aud: horizontally rather than a suooth sequence frozL left to right.RMCU-V-31 RWCU-V-34 RWCU-P-1A RMCU-P-1B RWCU-V-40 RWCU-V&2 RWCU-V-44 RWCU-V-100 RWCU-V-104 RMCU-V-106 (Itezi 462)(Iten 457)(Itez 450)(Item 455)(Itea 456)(Iten 460)(Iten 461)(Iten 458)(Iten 451)(Iten 453)1)Rearrange the following.RWCU control switches per the attached configuration draw-ing+IV ENG.40 CONST.119 2)The two RWCU system con-ductivity, recorders (G33-R601 and R603)are reverse of normal convention (outlet before in-.let).2)None IV NA 2)This is not considered to he a significant pro-blem.3)Enhancement is inadequate.

3)Add mimic, demarca-tion lines and other en-hancements as defined in Enhancement Guidelines.

NA 3)WPPSS to perform.

~c'age pZ of 9 Category.I-Safety Related, Minimum Opportunity to Correct Error Category II-Safety Related, Some Opportunity to Correct Error Category III-Reliability Related, Minimum Opportunity to Correct Error Category IV-Reliability Related, Some Opportunity to Correct Error Category V-No Impact on Safety or Reliability In Terms of Need: Category 1-To enhance safe operation, the change should be made.~Remove or mitigate discrepancy

~Provide error feedback to the operator~Increase time to respond to error l Category 2-To enhance safe'.operation, the change should be made.Category 3-To enhance reliable operation, the change may be desirable.

~Remove or mitigate discrepancy

~Provide error feedback to the operator~Increase time to respond to error Category 4-To enhance reliable operation, the change may be desirable.

Category 5-Change may improve operations.

a.High b.Medium c.Minimal Risk Assignment Based on: Guidance in draft NUREG-1580, 0659&0700.NRC audits of other control rooms.BWR Owner's Group decisions.

Note 3)Schedule to Com lete I 1.Prior to fuel load 2.After fuel load 3.Never-A

~i~o

~~~~I:~~~~~~~~~~~~~~~~~~

Note 1)-~Cate ot HED Report No.Wlg Page Q of g Category..I-Safety Related, Minimum Opportunity to Correct Error Category II-Safety Related, Some Opportunity to Correct Error Category III-Reliability Related, Minimum Opportunity to Correct Error Category IV-Reliability Related, Some Opportunity to Correct Error Category V-No Impact on Safety or Reliability In Terms of Need: Category 1-To enhance safe operation, the change should be made.~Remove or mitigate discrepancy

~Provide error feedback to the operator~Increase time to respond to error Category 2-To enhance safe operation, the change should be made.Category 3-To enhance reliable operation, the change may be desirable.

~Remove or mitigate discrepancy

~Provide error feedback to the operator~Increase time to respond to error Category 4-To enhance reliable operation, the change may be desirable.

Category 5-Change may improve operations.

a.High b.Medium c.Minimal Risk Assignment Based on: Guidance in draft NUREG-1580, 0659&0700 NRC audits of other control rooms.BWR Owner's Group decisions.

Note 3)Schedule to Com lete I~1.Prior to fuel load 2.After fuel load 3.Never

~g~J h~I~~~i E a~L<t'(a S8 V V'0 4 r o J~P j r gr Date: TO From:

Subject:

jtl~l NTEROFFlCE MEMORANDtj M Ds~buu.n:

WASHINGTON PUBLIC POWER SUPPLY SYSTEM lZ EDC WNP.2 l EDC WNP-3jS CI Admin File EA Fredenburgj June 30, 1981~" 9(H.McGilton-90E B.A.Holmberg-Deputy Project Manager, Engineering WNP-2 904A B.Vanerem-926f BA Holmberg-90<

R.G.DaValle-Control Room Design Review Coordinator 906D sf(2)EAF/lb HUMAN ENGINEERING CHANGES TO PANEL P602 APE Da~RGD/lb

Reference:

The following Human Engineering Discrepancy (HED)reports are attached for your concurrence.

HED Report No.016 through 018 When your concurrence is received, I will prepare a formal letter of direction, for your signature, to Burns and Roe, Incorporated, to implement the subject changes.kjf CONCURRENCE d R Burns E Roe Engineering Control Room Review Task Force Member Supply System Operations Control Room Review Task Force Member Wt 102 ERR-A o

INTERNAL'DISTRIBUTION~~j.,',<;,"r r, qie'".GK Afflerbach

-927N-.'-'-""-:

.%)XvkHa=A06D=.-.g.-:,-

':,-GJF/lb..:.BAH/lb f-(2).-=THIS LETTER SATISFIES COMMITMENT NO.THIS LETTER IDOC)IDOES NOTI ESTABLISH k IIEW COMICITMENT.

~WPPSS CORRESPONDENCE NO.August 31, 1981 MPBR-RO-81-146 Hr.J.A.Forrest f.roject Director..'=:.-Burns 5 Roe, Inc.601 Williams Blvd.'ichland, WA 99352.RESPONDS TO: N/A RESPONSE REQUESTED BY: Sept.4 S ubject:.SUPPLY SYSTEM NUCl.EAR PROJECT NO.Z.HED REPORTS H13-'P602'

Dear Nr.Forrest:

'his letter is your authorization to diTect G~le t c to prepare one FDDR to cover the Human Engin e ing ou changes within panel H13-P602.The c o ot n olv any external BOP hardware, therefor's h d e involved.However, if during the'D pre at a BOP change is uncovered, a copy of the D wi 1 be transmitted to BKR for your incorporation into a The changes that ar e made on H13-P602 are's follows:~HED Reoort D-O 6-01 018 tern:No.1~1 y.o ED Reports., 016, 017 and 018 are attached for your r erence.The letter of direction to General Electric should be issued by September 1, 1981.This work is a part of.BER Task No.3810.1 Yery truly yours,~Q B.A;Holmberg Deputy Project Nanager, Engineering, WNP-2 BAH/G JF/111 cc: MNP-2 Files-w/attachment n-BP UTHDR: GJ Freeman FDR slGNATURE oF: BA Holmberg FOR APPROVAL OF APPROVED DATE~wev GK Affler c'L~-A Sums and Roe, lric.601 Williams BlvcL s Richisnd, Washington 99352 s TeL (509)9434200

Subject:

Work Order 3900WNP-2 Washington Public Power Supply System Contract No.2 Control Room Modifications Responds to: NA General Electric Company Nuclear Energy Division M/C 394 175 Curtner Avenue San Jose, California 95125 September 15, 1981 BRGE-2-RO-81-523 Response Req'd By: 9/26/81 Attention:

Mr.F.A.MacLean Ref erence: Supply System (B.A.Holmberg)to BSR (J.A.Forrest)letter, (WPBR<<RO-81-146), WNP-2 HED Reports/H13-P602 Gentlemen:

The referenced letter authorized Burns and Roe, Inc.to direct General Electric to prepare one Field Deviation Disposition Request (FDDR)to accomplish modifications to Pane1 HI3-P602 The modifications are a result of the Human Factors Engineering design review being performed by the Supply System.The required modifications are detailed in Attachment 1 to this letter.Tour response is requested no later than September 26, 1981.Please contact this office with any.questions you have concerning this matter.Very truly yours, FOR THE PROJECT DIRECTOR Nuclear Group Supv.JAO:BJVE:tw Attachment cc: B.A.R.G G.F.J P.E.A.J.Ho W.S.WNP-2 J H.Holmberg-Supply System-3 DaValle--Supply System-1 Freeman-Supply System-1 Cooper-Supply System-1 Fredenburg

-Supply System-1 M Miller-GE Site-1 Chin-BPA-1-A-16-File Ralphs-Supply System-1 0

APPENDIX B TYPICAL ANNUNCIATOR PANEL REVIEW DOCUMENTATION PACKAGE PANEL P602 Review Report HED Report Prioritization Criteria Letters of Direction~Pa e B-1 B-15 B-18 B-28 WNP-2 CONTROL ROOM PANEL ANNUNCIATOR REVIEW PANEL P602 Date: October 30, 1981 Rev.: 1 I.PURPOSE The purpose of this review was to evaluate the annunciators on P602 for the following:

-Annunciator Grouping-Annunciator Window (Tile)Color Prioritization

-Annunciator Window Wording-Annunciators that have multiple actuation inputs which are independent and can exist at the same time.-Need for Addition and/or Deletion of Annunciators II.SCOPE The scope covers all the annunciators for the systems controlled from P602.There are no R.G.-1.47 changes to the P602 annunciators.

III.FINDINGS A.Annunciator Grouping 1.Annunciator grouping on panel P602 is good.The only discre-pancy noted was that the Radwaste System annunciators were un-necessarily on both annunciators A5 and A13.Attachment 4 of this review shows the existing P602 annunciator grouping.B.Annunciator Window Color Prioritization 1.In general, the window color prioritization is good.Some in<<consistancies were, however, noted and are detailed in Attach-ment 1 of this review.2.There are eight (8)windows on annunciator A13 which are white.GE drawing 761E791AD specifies amber color for these windows.See Attachment 5 of this review for the specific windows.C.Annunciator Window Wording l.Annunciator window wording on panel P602 is good.Some minor discrepancies were noted, however, and are detailed in Attach-ment 2 of this review.Page 1 of 3-B-1 Rev.1 D.Annunciators Having Multiple Actuation Inputs 1.Eight (8)'nnunciators have multiple actuation inputs which are independent and can exist at the same time, which prevents the operator of being alerted to additional alarm conditions after one alarm comes in and remains in the alarm state.Attach-ment 3 contains a listing of the above annunciators.

Annuncia-tors with multiple inputs from redundant channels monitoring the same parameter are not listed in Attachment 3.E.Need for Addition and/or Deletion of Annunciators 1.There are four (4)RHR/RCIC annunciators on P602 which should be relocated to P601.IV.RECOMMENDATIONS A.Annunciator Grouping 1.Relocate three (3)annunciator windows as shown in Attachment 5.Attachment 4 shows"as-is" grouping.The proposed grouping lo-cates all RadWaste system windows on annunciator A13.2.Correct GE drawing 807E174TC, Rev.9 to show that annunciator A13-1.2 is actually installed in A13-1.1.NOTE: Proposed Annunciator Wording Changes are not shown in Attachment 5.B.Annunciator Window Color Prioritization 1.Make annunciator window color changes proposed in Attachment l.Justification is stated in Attachment 1.Attachment 5 also shows the proposed colors.2.Change the color of eight (8)windows on annunciator A13 from white to amber to conform to QE drawing 761E791AD.

See Attach-ment 5 for specific annunciator windows.C.Annunciator Window Wording 1.Review annunciator window wording as shown in Attachment 2.2.'ll acronyms and abbreviations shall be in accordance with the"WNP-2 Standard List of Acronyms and Abbreviations for Control Room Labels and Legend Plates".3.Correct any wrong spelling.4.Change all GE MPL Numbers to B&R Tag Number.Page 2 of 3-8

Rev.1 D.Annunciators Having Multiple Actuation Inputs 1.A determination should be made concerning th'e need for an annun-ciator"Reflash" capability or an acceptable alternative,'uch

'as administrative procedures.

Attachment 3 lists the annunciators having multiple and independent actuation inputs.E.Need for Addition or Deletion of Annunciators 1.Relocate the four (4)RHR/RCIC annunciators on annunciator A13 to P601.See Panel P601 annunciator review for the specific locations on P601.2.To allow room on P603 Annunciator Panel A7, relocate P603 annunciator A7-4.8 to P602 annunciator A13-6.1.ATTACHMENTS 2~Proposed Annunciator Window Color Changes Proposed Annunciator Window Wording Changes 3.-Annunciators Having Multiple Inputs 4.5 As Is Annunciator Arrangement (Grouping)

Proposed Annunciator Color Prioritization Page 3 of 3-B WNP-2 CONTROL ROOM Attachment 1 PROPOSED ANNUNCIATOR WINDOW COLOR CHANGES Panel P602 Window Number Window Wording Color Change Basis for Change A5-2.2 MS Line Monitors Downscale'Amber to White To be consistent with all other"Downscale" annunciators which are white.A5-3.3 Off Gas High-High Radiation Amber to Red Both the Off Gas"High-High" Radiation and the Off Gas"High" Radiation windows are presently amber.This change will also match the light colors on P604.A5-3.4 Off Gas Vent Pipe High-High Radia-tion Amber to Red Both the"High-High" and the"High windows for this parameter are presently amber.This change will also match the light colors on P604.~Qi A5-3.2 Off Gas Post-Treatment High-High Radiation Amber to Red Same as above.A5-1.5 Reactor Building Vent High Radia-tion Red to Amber Both the"High-High" and the"High" windows for this parameter are presently red.A5-2.5 Reactor Building Vent Monitors Downscale Amber to White To be consistent with all other"Downscale" annunciators which are white.A6-5.1 Recirc Drywell High Press Switc A In Test Amber to White Is an operator information annunciator.

A6-3.4 Flow Cont Valve A Hyd Power Unit Standby Hyd Pump Operating Amber to White Is an operator information annunciator.

-B-4-Page 1 of 2

WNP-2 CONTROL ROOM Attachment 1 PROPOSED ANNUNCIATOR WINDOW COLOR CHANGES Panel P602 Window Number Windo~Wording Color Change Basis for Change A6-5.5 Recirc Drywell High Press Switch B in Test Amber to White Is an operator information annunciator.

A6-3.8 Flow Cont Valve B Hyd Power Unit Standby Hyd Pump Operating Amber to White Is an operator information annunciator.

A6-6.7 ATWS A or B Test Switch in Test Amber to White Is an operator information annunciator.

A13-2.2 Reactor Bldg Floor Drain Sump Level C002B High-High White to Amber For consistency and to conform to GE draw-ing 807E174TC.

A13-1.3 A13-2.3 A13-3.3 A13-4.3 See Attachment 4 White to Amber'o conform to GE drawing 761E791AD.

A13-1.4 A13-2.4 A13-3.4 A13-4.4 See Attachment 4 White to Amber To conform to GE drawing 761E791AD.

Existing P603 A7-4.8 Proposed A13-6.1'nnunciator Loss of 125 VDC White to Amber Operator warning.-8-5-Page 2 of 2,

e.

PROPOSED ANNUNCIATOR WINDOW WORDING CHANGES Attachment 2 Window Number Existing Wording Proposed Wording A5-3.7 Reac Water Cleanup Pump Flow High/Low Reac Water Cleanup Pump Flow Low.~, Existing A5-1.8 Proposed A13-4.2 Radwaste Controller 1 Trouble Radwaste Logic Controller 1 Trouble.Existing A5-2.8'Proposed A13-5.2 Radwaste Controller 2 Trouble Radwaste Logic Controller 2 Trouble.Existing A5-3.8 roposed A13-6.2 Radwaste Controller 3 Trouble Radwaste Logic Controller 3 Trouble.A6-4.1 ecirc Motor A Lockout Bus Under Volt-ge Recirc Motor A Breaker Aux.Trip Cir-cuit Under Voltage.A6-4.5 ecirc Motor B Lockout Bus Under Volt-ge Recirc Motor B Breaker Aux.Trip Cir-cuit Under Voltage.A6-5.5 ecirc Drywe11 High Press Switch In est Recirc Drywell High Press Switch B In Test.>~-B-6-Page 1 of 1 WNP-2 CONTROL ROOM ANNlJNCIATOR REVIEW At tachment Page 1 of 2 Panel/Annunciator Annunciator Meaning Remarks P602 A5-4.7 Reactor Water Cleanup Pump Cooling Water High Temperature Actuated by high temperature on either RWCU pump.P602 Reactor Building High Radiation Actuated by any 1 of 13 ARM'.A5-3.1 P602 Turbine Building High Radiation Actuated by any 1 of 5 AR?1's.A5-4.1 P602 Radwaste Building High Radiation Actuated by any 1 of 9 ARM'.A5-5.1 P602 Area Radiation Monitors Downscale Actuated by any 1 of 30 ARM'.A5-6.1-B 0

WNP-2 CONTROL ROOM ANNUNCIATOR REVIEW'ttachment 9 Page 2 of 2 Panel/Annunciator Annunciator Meaning Remarks P602 Remote Shutdown Transfer Switch In Emergency Position Actuated by any 1.of 20 switches.A5-l.6 P602 Recirculation Motor A/B Ikigh Temperature Actuated by any 1 of 12 temp sensors on either pump.A6-6.6-B "AS'X GEHENT<<.ttachment 4 AtIAllN:IATDA h5-BOARD P602 Page 1 of 3 U7 u lO<eeurlTng F loor Area Ill gh Aadlat lo>>(lew Fuel Storage N.ea Ii lgh adiatlon Reactor Building II I gh Aadlat lon TUI'bine OUI 1 ding Ill gh I a<i la t Ion adwaste Dui l ding Ill gh Radiation/f Area I adi a t Ion Honitors I<ownscale

~FaTn Stea~Line Iligh Aadlatldn/P Hain Stea<<<L lne Honl tors Downscale Off Gas Post Treatment Ill gh-II I gh R ad l a t Ion Off Gas~Post Treatment Iligh Radiation Off Gas.Post Treatment Flow!I I gh/Low Off Gas Honl tors Downscale or Inoperative Off Cias Post Treat<qent II I qh-Ill gh-II I gh Aadlat Ion Reactor Dulldlng Vent Sample F low Illgh/Lnw Off Gas II I gh-II I gh Radiation Dff Gas III gh Radl ation AIIR Radlat ion 8 Off Gas Post Treatment Honl tors Downscale Reactor Building Vent II I gh-III gh Radlat lon g Carbon Be<I Vault Ill gh Radlat ion Dff Gas Vent Pipe III gh-II I gh Radl at ion Off Gas Vent Pipe Illgh IIadlat ion Carbon Bed Vaul t Honl tors Downscale ul Off Gas Vent Pipe Honl tors Downscale Reactor Building Vent Ill gh Radl ation Reactor Building Vent Honl tors Downscale Off Gas Vent Pipe Sample FLow II I gh/I.ow Off Gas Sample Flow II I gh/Low RIIA Honl tors Downscale Or Inoperative Reactor Bul l ding CC Mater Honltors Downscale or Inoperative Denote S<utdown Transfer Switch In Emergency Posl t ion Aadwaste EFfluent Illgh Radl a t Ion Service Mater Ef fluent Ill gh Radiation g Reactor Building CC Mater lllgh Aadiation.

Service Mater Effluent Honitors Inoperative Inoperat I ve Aadwaste Effluent Honi tors Downscale or Inopera t I ve filler Oceln Inf Iuent Conductivity Illgh/Low Filter Demln Ef f luent Conducti vl ty Ill gh/Low Reac Mater Cleanup Pump Flow Ill gh/Low Reac Mater C1eanup Pump Cooling Mater Illgh Temp Reac Mater Cleanup Pump Olsch Pressure III gh/Low Cleanup Filter Oemin Fa I lure A ad<<as to Cu>>l col lor I 1<uuhle Aa<lwas te Control ler 2 Trouble Aadwaste Control ler 3 Trouble SPEAR SPARE Cleanup F I I ter Inlet Illgh Temp v/W-White A-Amber R-Red

~o 0"AS L GEHENT At t"-~'.:L".et'.t Page 2 of 3 ANNUNCIAIOB A6-BOARD P602 SI'ANF.leclrc Pomp A Seal Cool lng Mater Low Flow Rcclrc Pmnp A 1r lp ATMS In I t lated Reclrc Puny A Outer Seal lllgh Leakage 8 Re circ Hotor A Bearing Ol1 Ill gh Level Reclrc Puny A Seal Staging Flow lllgh/Low Re circ Hotor 8 Bearing Oil Low Level Reclrc Hotor A Ill gh Vlbrat lon PARE eclrc Puny 8 eal Cooling ater.aw Flow'Reclrc P(nnp 8'Ir lp AlMS ln1 t late(l Reclrc Pump 8 Outer Seal lllgh Leakage Re circ Hotor 8 Bearing 011 lligh Level Reclrc Pump 8 Seal Staging F low Il1gh/Low (q'(!c irc H(ltur 8 Bearing Ol I Low I.eve 1 Recim Hotor 8 Ill gh Vibration/V Icclrc Hutor A lib(ding l ll(l I a(l t t.(:ok age Ieclrc Hotor A ockout Bus Under Voltage le circ)rywe1 I High Press Switch A ln Test y Reclrc Hotor A Minding Coolant Low Flow/t(Recirc Hotar A Bkr Trip Clrcul t Under Voltage g System A Drywe1 I!Ilgh Pressure Interlock Flow Cont Valve A llyd Power Unit Startup Inhlb I ted Reclrc Hotor A Overcurrent Or Ground Flow Cont Valve A Hotlon lnhlb I ted F low Cont Valve Ieclrc Hotar 8 A llyd Power Ilndlng Unit Standby 4 aolant Ilyd Pony Operatln Leakage Flow Cont Valve ecirc Hotor 8 A llyd Power ockout Bus Unit Control nder Voltage System Abnormal g 8 F1ow Cont Valve eclrc A Haxlm(nn rywel I Ill gh Open Llml ted Press Switch ln Test Reclrc Hotor 8 Mind)ng Coolant-Low Flow Reclrc Hotor 8 Bkr Trip Circ ul t Under Voltage g System 8 Orywell lllgh Pressure interlock FLow Cont Valve 8 llyd Power Unit Startup lnhlb1 ted Reclrc Hotor 0 Overcurrcnt or Ground Flow Cont Valve 8 Hot ion lnh lb I ted Flow Cont Valve 8 Ily(I Power Unit Standby llyd Pulnp Opcral lng Flow Cant Valve 8 Ily(l Power Unit Control System Abnormal g Flow Cont Valve 8 Haxlmum Opeil L lml ted low Cont Valve A Servo Input Control Signal Ahno(mal FLux Controller Output Signai Abnormal Haster Controller Output Signal Abnormal g SPARE low Cont Valve D Servo Input Control S lgnal Abnbrmal Reclrc P(nnp/Ho tor hor8 ill gh Te(np ATMS Aor 8 Test Switch In Test Reclrc System Approaching Auto Flow Range L l(nl t gp W-White A-Amber R-Red

~~"Ab L RANUL:tlEH'L'tt

...en', Page 3 of 3 ANNNNCIATOR A13-AOARO P602 F'/@Toe 8gDg FÃboR DRr?rHamp LEAL MIGrr-S/i g H?Cactor Ridg I loor Brain Stipe I.evel (COA2A)ligh-lligh Reactor 01dg Floor Brain Swy Level (C0020)II I gh-ill gh Reclrc Pump A Lou Speed Auto Transfer CKT Not Avail p Raclrc Pomp Hotor A Auto Transfer lncomp le te Reclrc Pump 8 Low Speed Auto Transfer CKT Not AvalllReclrc Pump Hotor 8 Auto Transfer inc omp le te Recirc Hotor A Breaker Trip Re circ Hotor A lockout Ileactor Bldg Fqulp Ora ln Sump ligh Level W SPARE Reclrc Pump HTR A Auto Trip Or Transi'er to Low Speed Reclrc Pump SPARE HLR 8 Auto Trip Or Transfer to LoM Speed leactor Bldg Equip Orain Sump Nigh Temp Ltl , ITIC l~4'44 8 sire<m'~P HIGH LFVFC W)PCiC To grhP rf/p sf~~f+Ari/f rglr LFuFL SPARE acre ro Pl/IZ 8 5g~p rddP 0'~GA?rli~<E'fv AFuFZ 4i~>Reclrc HG Set A Protective Relay Trip lt/Reclrc HG Set A Inter lack Bypass SPARE Reclrc HG Set 8 Protective Relay Trip gl Reclrc HG Set 8 Interlock Bypass SPARE Re circ Hotor 8 Breaker Tr lp ileclrc Hotor 8 l.ockout SPARE~>I-Hhite A-Amber R-Red

PROPOSED ARRANGEM)D COLOR PRIORIZATION At ent 5 nlvaO<CInTOA SS-RO~AO P6OS Pape)of 3 ARM~un 7n IC g I')nor Area III gh II a<liat IUI<<Iew Fuel Stnraqu brea II lgh Ra<I)ation A HaTn Stea<<>L lne lilgh A ad la t Ion Hain Stea<I L lne Hon)tars Oownscale PR))Of f A<as Post Treatment II I qh-II I gh-ill gh Radiation Reactor Oulldlng Vent Sa<<y le Flow Illgh/Lnw Aeactor Oui ldlng Vent II I gh-III gi>A ad)at Ion Carbon Oe<l Vault Ill gh Radla t Ion Reactor Building Vent III gh A ad l at Ion Reactor Ou))ding Vent Honltors Oownscale e<<<ote Shutdown Transfer Switch ln Ea<ergency Position Aadwaste F.f f luent lllgh Aad)at ion lnf luont Conductivity Illgh/Low F I)ter Oe<<<ln Ef f lueut Conductivity II)gh/Low SPARE SPARE Reactor Aul 1 ding Ill gh IIadlat ion A Off Gas Post Treat<oent II I gh-Ili gh Radiation A Off Gas Off Gas Il I gh-Ill gh Vent Pipe Rad I a t Ion II)gh-III gh A Radiation A Off Gas Service Mater Aeac Mater Vent Pipe Ef f Iuent Cleanup Pump Sa<<<p le FLaw Ill gh Flow lllgh/Low A Aadlat Ion A lllgh/Low SPARE Turbine Aul ld)ng II I gh)ail)at)on A Aadwaste Ou))ding II I gh Aadl a t lou 0)'f Gas Post Treatment ll)gled Aadlat Ion A Off Gas Post Treat<<<ent Flow II I gh/Low RIIA Ill gh Radl at Ion Carbon Bed Vaul t Honl tors Oownscale W Of(Gas Off Gas Illgh~Vent Pipe Radlat lun'llgh A Rad1 a t I on A RIIA Mon)tars Oownscale Or inoperative Service Mater Effluent Honitor inoperative W inoperative W Off Gas Reactor Sample Flow Oulldlng CC II I gh/I.ow Mater lllgh A Radiation.

A Reac Mater Cleanup Pu<<<p A Cool lng Mater Illgh Te<<<p (2)W Reac Mater Cleanup Pump Olsch Pressure Illgh/Low Reac Water Cleanup Pump B Cooling Water SVAAL Area Indi a t)on Mon I tars Oawnscale W Off Gas Honl tors Oowuscale or inoperative W Off Gas Past Treat<aent Honl tars Oown sea le W Off Gas Vent Pipe Honl tors Oownscale Reactor Bu))d)ng Aadwaste fffluen CC Mater Honltors Honitors Oownsca1e or Oownscale or inoperative W inoperative Cleanup F I I ter Oe<p)n Fa I lure W Cleanup F liter inlet Illgh Te<<<p W Notes: (1).(2)W-White A-Amber R-Red Relocated to annunciator A13-P602 Existing annunciator A5-4.7 split into two (2)annunciators.

~,

Radwaste PROPOSED ARRANGEM D COLOR PRIORI ZATION Att ment 5 Mnii!ICIAT6I AI3-AOAAO P6I!2 Recirc.Reactor Bldg Floor Drain Sump Level~(C003)High-R1 Ile.lt'tor I g I loor Brain SOIIIp Iuvel (C002A)I I I gil-II I 9il AI!ac tor'Ill dg CIiulp Oraln SOInp Ilgh Level W SPARE Aeactor Bldg Floor Oraln SOIIy Level (C0020)Iilgh-ill gii A SPAAE Aeclrc Puny A Lou Speed Auto Transfer A CKT Iiot Avail(4 ROC lrC PIvt!p Hotor A Auto Transfer Inco!!y le te A(4)Aec lrc PuaIp HIA A Auto Trip Or Transfer to LoH Speed A(4)Aeclrc POIIy 0 LoM Speed Auto Transfer A CKT IIot Avail(4 Aec lrc Pivi!p Hotor 0 Auto Transfer Inco!Iylete A(4)Aeclrc Puny HIA 0 Auto Trip lir Transfer to Lolt Speed A(4)Aec lrc Hotor A Breaker Trip R Ae circ Hotor A Lockout SPAAE Ieactur Bldg I quip Oraln Si!Np lilgh feI!Ip W Radwaste Con Aeclrc HG Set A troller 1 Protective rouble Relay TrlP Aeclrc HG Set 0 Pro tec t I ve Aelay Trip A 4 Re circ Hotor 0 Breaker Trip R SPAAE W 2 Radwaste Controller 2 Trouble 2 3 Aeclrc HG Set A Interlock Bypass Reclrc HG Set 0 Interlock Bypass Rec lrc Hotor 0 Lockout Annunciator Loss of 125 VDC A (5)(2)Radwaste SPACE Controller 3 Trouble W (2)(3 SPAAE SPAAE Notes: (1)(2)(3)(4)(5)W-White A-Amber R-Red Currently in window 1.1.GE drawing 807E174TC Rev.9 specifies window 1.2.GE Drawing should be corrected.

Existing annunciator relocated to P601, see P601 annunciator review for specific location.Relocated from annunciator A5-P602.Windows are currently white.GE drawing 761E791AD specifies amber.Relocated from F603 annunciator A7-4.8.

Recirc A PROPOSED ARRANGEH)D COLOR PRIORIZATION Attachment 5 AOBUBCIAIOR AO-BOABO r6OZ Recirc B Page 3 of 3 SPABF.Rnclrc Pimii h I lr lp hfHS In I t la ted Reel rc Motor A Bearing Ol I Ill gh leyte.l A Recirc.Motor A Bearing Oil Low Level A PARE Beclrc Pinap 0 fr lp AlMS In I t I a teil Be circ Motor 0 Bear lng Ol I lllgh geve I Recirc Motor B Bearing Oil Lo Level A leclrc Puap A Sua I Cool lng Water Iuw flow A!i!circ Hutor h Ulndlng Coolant I i:.ik age A Rec lrc Puny A Outer Seal lllgh Leakage A Reclrc Hotor A Minding Coolant Low Flow A Reclrc Pump A Reclrc Motor A leclrc Puny 8 Seal 5 tag lng Ill gh eal Cooling Floe lllgh/Low Vibration later A A.ow Flow A Flow Cont Valve flow Cont Valve teclrc Motor 0 A llyd Power h Ilyd Po~er llndlng Unit Startup tlnlt Standby W oolant lnhlb I ted A llyd P<<ny Opera tin Leakage A Reclrc Pump 8 Reclrc Pump 0 Outer Seal Seal Staging Illgh Leak age F low Iligh/Low A A Reclrc Hotor 8 FLow Cont Valve lllnding 0 Ilyd Po~er Coolant Ihilt Startup Low F low A lnhlb I ted A Reclic Hutor 0 II I Oil Vlliratlon A Fliiw Cu>>t Valve ll Ilyil Puwur Un I t S t an<lhy Ilyil I'ump Operat liig (ec I rc Mo to r h Lockout Ous Under Voltage Reclrc Motor A Okr Trip Circ ul t Under Vol tageA Reclrc Hotor A Overcurrent Or Grouiid A Flow Cont Valve teclrc Motor 8 A llyd Po~er.ockout Bus Unit Control Jnder Voltage Systeia Abnormal A A Reclrc Hotor 8 Reclrc Hotor 0 Okr Trip Overcurrent Circ ul t or Ground Under Voltage A A Fliiw Cont Valve 0 Hyil Power Uii I t Cont ro I System hbnoraiaIA le circ trywel I High press Switch h ln Test W low Cont Valve h Servo IIII)lit Control Signal Ulllo linn I A System A Orywei I Ill gh Pressure interlock.A FLux Control le r Output S lgna I hluionaa I A Flow Cont Valve 0 Servo input Control Signal Abnormal A Haster Sphllf Controller Output Signal hbnorinal A Flow Cont Valve flow Cont Valve leclrc A Hot ion A Hax lanan)rywell lligh Inhlb I ted Open L lml ted Press Swl tch A A ln Test W System 8 Orywell Illgh Pressure interlock A Flow Cont Valve 0 Hot Ion Inh lb I ted Rec lrc ATHS pianp/Hotor hor8 hor0 Test Switch lllgh Teinp A In fest W Flow Cont Valve U Hax lmiim Ope>>L linl ted Roc lrc Systria hliliruach lug hutu Flow Range L linl t A W-White A-Amber R-Red

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~~I~~~~\~~~~~~~~I~~~\~~: '~~I'I I I I~'~~

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Note 1)-~Cate or HED Report No.Page/of Category Safety Related, Minimum Opportunity to Correct Error Category II-Safety Related, Some, Opportunity to Correct Error Category III-Reliability Related, Minimum Opportunity to Correct Error Category IV-Reliability Related, Some Opportunity to Correct Error Category V-No Impact on Safety'or Reliability In Terms of Need: Category 1-To enhance safe operation, the change should be made.,~Remove or mitigate discrepancy

~Provide error feedback to the operator~Increase time to respond to error Category 2-To enhance safe operation, the change should be made.Category 3.-To enhance reliable operation, the change may be desirable.

~Remove or mitigate discrepancy

~Provide error feedback to the operator Increase time to respond to error Category 4-To enhance reliable operation, the change may be desirable.

Category 5-Change may improve operations.

a.High b.Medium c.Minimal Risk Assignment Based on: Guidance.in draft NUREG-1580, 0659&070(NRC audits of other control rooms.BWR Owner's Group decisions.

Note 3)Schedule to Com lete 1.Prior to fuel load 2.After fuel load 3.Never COD wHT w HT'eac Water Cleanup Pump A Cooling Water High Temp Reac Water Cleanup Pump B Cooling Water High Temp Reference Drawing 807E175TC HED Report No.036, Item 3 Page~of 5'B HED Report No.036 WNP-2 CONTROL ROOM ANNUNCIATOR REVIEW Attachment 1 Page 1 of 2 Panel/Annunciator Annunciator Meaning Remarks P602 A5-4.7 Reactor Water Cleanup Pump Cooling Water High Temperature Actuated by high temperature on, either RWCU pump.Reactor Building High Radiation Actuated by any 1 of 13 ARM'.A5-3.1 P602 Turbine Building High Radiation Actuated by any 1 of 5 ARM'.A5-4.1 P602 Radwaste Building High Radiation Actuated by any 1 of 9 ARM'.A5-5.1 P602 Area Radiation Monitors Downscale Actuated by any 1 of 30 ARM'.A5-6.1-B-20" HED Report No.036 WHP-2 CONTROL ROOM ANNUNCIATOR REVX~Attachment 1 Page 2 of 2 Panel/Annunciator Annunciator Meaning Remarks'602 Remote Shutdown Transfer Switch Xn Emergency Position Actuated by any 1 of 20 switches.A5-1.6 P602 Recirculation Motor A/B High Temperature Actuated by any 1 of 12 temp sensors on either pump.A6-6.6-8 "AS ARRANGEHENT Ar.tac'nmerit 2 A<lAIAICIATOA AS-BOMB P602 HED Report N 6 Page 1 of 3<eeueITrig I'oni'rea ill gh Aadlatlo>>llew Fuel Storage h<ea<I lgh Aad1 at Ion Reactor Aul Id l<<g Ill gh II adl at lon HaTn Steam L ine ill gh Aadiatlon/P Hain Stea<<<Line Honl tors Downscale Off Cas Post Treatment Ill gh-III gh Radiation Of(7>as Post Treatme>>t Il I qh-III gh-II I gh Aadlat ion Reactor Building Vent Sa<qile F low III gh/Lnw Off Gas Il I gh-ll!gh Rad I a t I on Reactor Building Ve>>t II I gh-II I gh Aadlat ion Carbon Oed Vaul t Ill gh Rad la t Ion Off Gas Vent Pipe Ili gh-III gh Radl at Ion Reactor Building Vent III gh Aadi a t ion Reactor Building Vent Honitors Downscale Off Gas Vent Pipe Sample FLow lllgh/Low Remote Shutdown Transfer Switch In Emergency Position Aadwaste Effluent lligh Radiation Service Mater Effluent III gh Aadla t ion g HF I ter Demln Inf lue>>t Cond>>cti vl ty lllgh/Low F liter Oemln Ef fluent Conductivity lllgh/Low Reac Mater Cleanup Pump F'low ill gh/Low Aadwaste Cu>>l ro I ler I I<'u<dile Aadwaste Controller 2 Troub I e Radwaste Controller 3 Trouble Tu<blue Building II lgh Iadiatlon OI'f Gas Post Treatment Ill gh Radiation Off Cas Ill gh Radiation Off Gas Vent Pipe Ill gh!Iadiatlon Off Gas Aeactor Sample Flow Building CC II I gh/Low Mater lllgh/<<'adiation.

Reac Mater Cleanup Pump Cooling Mater Iligh Temp SrnAE adwaste Bui lding Ill gh Radiation/f Area Radiation Honi tors Downscale~Off Gas Post Treatment Flow II I gh/Low Off Gas Honitors Downscale or inoperative RIIA Ill gh Radiation Off Gas Post Treatment Honl tors Downscale Carbon Bed Vault Honltors Downscale L<l Off Gas Vent Pipe Honltors Downscale RIIA Honi tars Downscale Or Inoperative Reac tor Building CC Mater Honitors Downscale or Inoperative Service Mater Effluent Honitors Inoperative lnoperat I ve Aadwaste Effluent Honitors Downscale or inoperative Reac Hater Cleanup Pump O lsch Pressure lllgh/Low Cleanup F I I ter Oemln Fa I lure SPARE Clean>>p Filter Inlet Iligh Temp H-Ifhite A-Amber R-Red

0"AS ARRANGEMENT A L~e)11(lierlt 2HED Report N Page 2 of 3 AIIIIUIICIAIOR A6-00ARO P602 SI'ARF.Ieclrc Pu(np A Seal Cool ing Water I.ow Flow Inc)re Motor h IIIndlng C(1(11 an t L<<ok age Iec)rc Hotor A ocknut Bus lieder Vo itage Ie circ Irywe I 1 Ill gh Press Switclr h In Test y low Cont Valve h Servo Input Control Signal Abnormal Roc)re P(nnp h Trip ATWS in)t lated p Recirc Puny A Outer Seal Illgh Leakage 8 Roc)re Hotor A II)nding Coolant Low Flow Recirc Hotor A Bkr Trip Circuit Under Voltage g System A Orywel 1.'I 1gh Pressure Interlock FLux Controller

.Output Signal Abnormal Re circ Hotor A Bearing 0)1 Illgh Level Recirc Pump A Seal Staging F low II)gh/Low Flow Cont Valve A Ilyd Power Un I t 5 tar tup lnh lb I ted Reclrc Hotor A Overcurrent Or Ground Flow Cont Valve A Hot)on lnhib I ted Haster Controller Output Signal Abnormal Rec)rc Motor 0 Bearing Oil Low Level Reclrc Hotor A Ill gh V)bra t)on Flow Cont Valve A Ilyd Power Unit Sl.andby Ilyd Pony Operatin Flow Cont Valve'A llyd Power Unit Contro I System Abnormal g Flow Cont Valve A Hax)mum Open Llml ted~FP SPARE PARE eclrc Puay 8 eal Cooling ater.ow Flow Iec I rc Ho tor 8 Iinding oolant leakage Iecirc Motor 8 ockout Bus nder Voltage 8 ecirc rywel I II I gh Press S~itch In Test Flow Cont Valve 0 Servo Input Control S igna1 Abnormal Reclrc Pun(p 8 Tr lp ATQS ln I t I a te(l Reclrc Pump 8 Outer Seal Iligh Leakage Reclrc Hotor 8 II)nding Coolant Low Flow Recirc Hotor 8 Bkr Trip Clrcui t Under Voltage~System 8 Orywell lllgh Pressure Interlock Rec)re P(nnp/Ho tor Aor8 II I gh Te(np Re circ Motor 0 Bearing 0)1 Illgh Level Recirc Pump 8 Seal Staging Floe Illgh/Low H Flow Cont Valve 0 Ilyd Po~er Unit Startup lnhlbl ted Reclrc Hotor 0 Overcurrent or Ground Flow Cont Valve 0 Hot)on lnhib I ted ATIIS hor 8 Test Switch In Test R((c lrc Motor 0 Bearing Oil Lnw I.eve)Rec)rc Motor 0 II)gh Vlhl ation i/Flow Cont Valve 0 Ily(l Power Unit Stan(lby llyd Pump Operating Flow Cont Valve 0 Ily(l Power Unit Control System Abnormal p Flow Cont Valve 0 Haxlmu(a Open Limited Rec)re Systo(a Approaching hi(to F low Range L)ml t W-White A-Amber R-Red

.

"AS RRANGCHENT At tac.Imert 2 HED Report No.Page 3 of 3 ANNIINCIATOR A)3-BOARD P602 ,rrrrc4t g'r Dg glOaN Dr2rIirr S'u~W<Fur-'y/Grr

-irir,l/Reactor II ldg I'loor Brain Sump l.eve 1 (C002A)II igh-Ill gh IIeactor Bldg Fqulp Drain Sump Iligh Level W Ieactor Bldg Equip Drain SImy Iligh Temp Nl./.rc ry)PION 8'ir~~rrrrI P dicrI r f vs W Eddic ro/PrrÃ8/p 5ffgn rg'i~re rr rg'rr LFvFr-Reactor Bldg Floor Drain Suay Level (C0020)Ill gh-Ill gh SPARE SPARE Werc ro Orris B Sg~Fenrir ri'~G~6 C'gZl-A?c'rc WuR8i~F F<A'P+gp l,gg gF'vrZ/id+lr Recirc Pump A Low Speed Auto Transfer CKT llot Avail p Rocirc Pump Hotor A Auto Transfer lncomp le te Reclrc Pump HTR A Auto 1'rip Or Trans('er to Low Speed Reclrc HG Set A Protective Relay Trip lII Reclrc HG Set A interlock Bypass SPARE Reclrc Pump 8 Low Speed Auto Transfer CKl'ot Avail~Reclrc Pump Hotor 8 AiIto Transfer incomplete Recirc Pump HN 8 Auto Trip Or Transfer to Low Speed Reclrc HG Set 8 Protective

.Relay Trip gl Recirc HG Set 8 interlock Bypass SPARE R eel rc Hotor A Breaker Trip Recirc Hotor A Lockout SPARE Recirc Hotor 8 Breaker Trip ilecirc Motor 8 Lockout SPARE~>J-Hhite A-Amber R-Red

~o 0 PROPOSED ARR~"~PV>~"O'..OR PRIORITIZATION AAAIIACIATW hs-DOAAO P6OP HED Report No'age 1 of 3 Iti~!iic ing f lnor Area II I gli Aailiatioii A flew fuel Storagr Area II igli Aa<liat ion A L lne II I gli Aad la t Ion R Hain Steam L lne Honl tors Oownscale Ofr Gas post Treatment II I qh-II I gh-II I gh Aadlat ion Reactor Oui 1 ding Vent Samp le F low Ill gli/Low Aeactor Oui ldlng Veiit Ill gh-III gh A ad I a t Ion Carbon Deil Vaul t Ill gh Aadl a t Ion.Reactor Building Vent III gh Aadl at ion Reactor Building Vent Honl tors Oow>sca le emote Shutdown Transfer Switch In Emergency Posl t ion Aadwaste F f f luent Ill gh Aadlat lon Fl tcr Ocmln Inf luent Conduct I v I ty lllgh/Low Filter Ocmln Ef fluent Conductivity Iligh/Low SPARE SPARE Reactor Dul ldlug II I gh Dad l at lou Iurb lne llu I I ding II lgh l ail la t I on A Iadwaste Dul lding III gh Radiation A Off Gas Post Treatment II I gh-III gh Radiation A Off Gas Post Treatment lllgh Aadlat Ion A Off Gas Post Treatment Flow II I gh/Low A Off Gas II I gh-II I gh Radiation A Off Gas ill gh Radiation A AIIA Ill gh Radlat lon A Off Gas Vent Pipe III gh-II I gh Raiilat lon A Off Gas Vent Pipe Ill gh Radiation A Carbon Bed Vault Honl tors Oownsca le Off Gas Vent Pipe Sample FLow II I gh/Low A Off Gas Sample Flow II igh/Low A RIIA Honl tors Downscale Or inoperative Service Mater Aeac Mater E f f luent Cleanup Pump III gh F low Aadlat lon A Illgh/Low M Reactor Reac Mater Oulldlng CC Cleanup Pump A Mater lllgh Cool lng Mater Radiation.

A lllgh Tscp (2)M Service Mater Reac llater Effluent Honitor Cleanup Pump lnopera t I ve 0 I sch Pressure lnoperat I ve M Ill gh/l.ow SPARE Reac Mater Cleanup Pump B Cooling Water qh Zeus~SPARE Area Andi a t Ion Non I Lors llownsca le W Off Gas Honl tors Downscale or Inoperative M Off Gas post Treatment Honltors Oow~sca le M Off Gas Vent Pipe Honl tors Oownscale Reactor Bui1dlng CC Mater Honltors Oownscale or inoperative M Aadwaste Effluen Cleanup Filter Honl tors Oemin Downscale or Failure inoperative M CIeanilp F liter Inlet lllgh Temp M Notes: (1)(2)W-White A-Amber R-Red Relocated to annunciator A13-P602 Existing annunciator A5-4.7 split into two (2)annunciators.

.

Radwaste 0 PROPOSED ARRANGEH 0 COLOR PRIORITIZATION Attachment 3 AIIIIIIIICIATOA AI>-AOAAO r602 Recirc.IIED Report No Page?of 3 Reactor Bldg Floor Drain Sump Level~(C003)High-I.g Itcaftor i g I loor IIrain Sump I eve l (COI)2A)II igh-Illgh lIcactor Illdg (4lulp Ora In Sump II lgh Levc I W SPARE Aeactor Bldg Floor Oraln Swy Level (C0020)Illgh-Illgh A SPAAE Aeclrc Pump A Lou Speed Auto Transfer A CKT riot Avail(4 Acclrc Pump Hotor A Auto Transfer lucomp le te A(4)Aeclrc Pump HTA A Auto Trip Or Transfer to LOH Speed A(4)Aecirc Pump 0 Lou Speed Auto Transfer A CKT Hot Avail(4 Aeclrc Pump Hotor 0 Auto lrausfer Incomp le te A(4)Aecirc Pump HIA 0 Auto Trip Or Transfer to LOH Speed A(4)Aec lrc Hotor A Breaker Trip R Aeclrc Hotor A Lockout SPARE tcactul Bldg Radwaste Con LqulP Brain S<m~P troller 1 Trouble W Aeclrc HG Set A Protective Relay Trip A4'eclrc HG Set 0 Protective Relay Trip A 4 Ae circ Hotor 0 Breaker Trip R SPARE W 2 Radwaste Controller 2 Trouble 2 3 Aeclrc HG Set A Interlock Bypass A Reclrc HG Set 0 Interlock Bypass A Rec1rc Hotor 0 Lockout Annunciator Loss of 125 Controller 3 VDC Trouble A (5)(2)W (2)(3 SPARE SPARE SPAAE Notes: (1)(2)(3)(4)(5)W-White A-Amber R-Red Currently in window 1.1.GE drawing 807E174TC Rev.9 specifies window 1.2.GE Drawing should be corrected.

Existing annunciator relocated to F601, see P601 annunciator review for specific location.Relocated from annunciator A5-P602.Windows are currently white.GE drawing 761E791AD specifies amber'.Relocated from P603 annunciator A7-4.8.

.o-~

PROPOSED ARRAN(xEMF At chment 3 D COLOR PRlORlTIZATION HED Report No.:-age: of 3 Recirc A htlldlflclhlOR A6-BOARD P602 Recirc B Sl AOC Rrclrc P<<aa I h I Ir ip ATMS ln I t lated Rect rc Hotar A Rearing Ol 1 II I gh A,eyr.l A Recirc.Motor A Bearing Oil Lov Level A PAIIE Reclrc P<<anp 0 Tr lp ATIIS In I t I ate<i Re circ Hutor 0

Dear log Oil ill gh/eve I Recirc Motor B Bearing Oil Lo Level A leclrc Puny A Soa I Cool lng Mater I<<<<w F low A I<<.cl<<.c Hutor h Il lading I<<1<<<<I J<<l t I<<.<<k a<<je A Dec lrc Puny A Outer Seal High Leakage A Rcclrc Hotor A Minding Coolant Low Flow A Rcclrc Pump A Seal Staging F low ll1gh/low A Flow Coot Valve A llyd Po~er Unit Startup lnhlb I ted A Reclrc Hator A II I gh Vlbra t lon A Flow Cont Valve:

h Ilyd Power Unit Standby W llyd Pony Operatln leclrc Puay 8 eal Cooling later ow Flow A leclrc Hotor 0 l lndlng ool ant leakage A Reclrc Pump 8 Reclrc Puny 8 Outer Seal Seal Staglllg Illgh Leakage Flow Iilgh/Low A A Reclrc Hotor 8 FLaw Cont Valve lllnd lng D llyd Power Coolant Dolt Startup Low F low A Inhib I ted A Rcclrc Hotor 0 II I gh VII)rat lon A I'l<<<<w Co<<<<t Valve 0 Hy<<l Power U<<1 I t 6 t a<<IIII<<y Uy<<l I'ump Opcrat log (eclrc Hotor h Lncknut Ous Ih<<der Voltage Reclrc Hotor A Okr Trip C lrcul t Under Vol tageA Reclrc Hotor A Overcurrent Or Ground A Flow Cant Valve teclrc abator 8 h Ilyd Po~er ockout Bus Unit Control lnder Vol tage Syste<<a Abnormal'A A Reclrc Hotor 8 Reclrc Hotar D Okr Trip Overcurrcnt Circ ul t or Ground Under Voltage A A Fl<<<<w Cont Valve 0 Ily<<I P<<lwcl Unit Control System hhoor<<nay Ic circ Irywe I I Iligh I Iess Switch h ln Test W System A Drywell lligh Pressure Interlock A Flow Cont Valve A Hot lan Inhlb I tcd Flow Cont Valve leclrc A Hax l<<aum rywe1 1 II I gh Open Ll<<al ted Press Switch A ln Test W System 8 Orywell lllgh Pressure Interlock A Flow Cont Valve 0 Hotlon Inhlb I ted Flow Cont Valve 0 Haxlmom Ol<<co L lml ted'low Cont Valve 4 Servo I<<yot Control Signal V<<oo nna I A FLux Controller Output Signal Aboor<<aa I A Haster Controller Output Signal hbnor<<aa1 A SPIC Flow Cont Valve 0 Servo Input Control Signal hbnorma I A Rec lrc ATII5 Pmap/Hat or harB Acr 0 Test Switch illgh Te<<ap A ln Test Rccirc Systrm hp))roaching Auto Flow Range Ll<<alt W-White A-Amber R-Red

~o I NTL.ROFFICE MEf~IORAND0 M%'ASHINGTON PUBLIC PO>VER SUPPLY SYSTEM F-81-9694 Distribution:

0 EDC WNP-1/4 Kl EDC INPUT CI EDC WNP4J5 CI Admin File Dater Tot From:

Subject:

November 2, 1981 GJ Freeman, Control Room Program Manager RG DaValle, Control Room Design Review Coordinator HUMAN ENGINEERING CHANGES P602-ANNUNCIATOR SYSTEM PANELS L Carey-9179*WP Gilles-906D CH McGilton-906D 8 Van Erem-926 EAF/LB~.RGD/LB sf (2)pf Relexence:

The following Human En'gineering Discrepancy (HED report is attached for your concurrence.

HED Report No.036 The Task Force will be available to discuss and resolve any concerns you might have on the recommended changes.When your reviews are completed, a letter of concurrence is re-quired for our files to identify approved HED changes.RGD/jca Concurrence:

Burns 8 Roe Engineering Control Room Review Task Force Member'pply System Operations Control Room Review Task Force Member 8-28-wp loa Ra

~s APPENOIX C WNP-2-CONTROL ROOM PICTURES

~o 7I E: fh~~PANEL P601 ECCS SYSTEMS (LEFT SIDE)h~m sauceasa4@55aaa aa VV+VlV W WW~0 W lg ko/h 4,4 4 4 4 k 441%4+,IQ,1444

~F~~>>~4~~ih~Cn A aA I I IIht I

.~o PANEL P601 ECCS SYSTEMS (RIGHT SIDE)

.

PANEL P602 REACTOR WATER CLEANUP AND RECIRCULATION SYSTEMS PANEL P603 REACTOR CONTROL SYSTEMS e T.

.i ISEitKXiiiitlSIBIH hQWIAE38$CQkiit.@%EitkSSN5@ilkQ'%khk5katHIRSRR-hiQSQNRWliiQhQCI CB the-'-)ling~j I~I j~]4~g j'~.: RilRfhlKilKR

'%@%l&hS&laat SSCCliSRRRiE3 gggQgggggg~

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))))l)SW))')~V tbw-0 o 0 xQi<<<<~~<<)XX<~,'.PANEL P840 REACTOR FEEDWATER AND MISC SYSTEMS (RIGHT SIDE)PANEL 820 l MICELLANEOUS SYSTEMS (LEFT SIDE)W4<<<<>>,>>m'z-'~~~'~-;J>>A W A w<<h..ww.,~.g.>>y~,+gal ,x,'Zp~~e,-~~,*>4'<<w fA,fj j;x'j>f'iA>>x ky'"jv"'c 0'.k J,9.~..g<<'<<,<<<<J W.J.~,<<~<<.p'gP+Pg>PE~x<<p"q P~~*-<>>" t5~'x 4%k<<lA>><<<<>>t4.A~+~+@4@g cj~l QQQQQ~~~CA<<<<<<ci%4L 0~4 V$<<<<pl<<<<<<x~f'

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'jiiiijii(liiii1 1 5)*V~K4~'t' 44>><<>>/PANEL P800 ELECTRICAL PANEL (LEFT SIDE)4 l[,>>4.>>.'.+>>>>'-;W 4 Fi~<<~~~'444'<<>>~I~~QT>>+4~.C>>'l<<~l<<<<4>>5~e-ale<<<<<<>>P't0~~Vs<<I,PP>>l g~>:>><<>>P 4 y<'4<<>>>>i et~'-g'~4~,",,~'-.<<4,>>>>.yy.'~~>><<gK~p<<4>>2<<.WtN~&vÃ~~~~k

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',.=>>i~~~,~t." 5'~~a Kl Q)R CD Im I C/)m tO CD-I mm n 5 5t-" ,5 5 5 5'54 A5-.5'5 ,5'k--~W,4t 55>>t+W+p/Cp.tI~5i-'>>t5t t5t>>C~+~~>W 5+>>>>5w" Qi>>M~xW~C 5>>C~.>>t t'>>Y-5 vv t5 5~~'".'>>5-.>>->>~M-t-">>t,-'5-'"5 4'l>>'>>-.5 H'5*'>>">>>>)3 6 v5")PC'5"'

PANEL P672 OFF-GAS CONTROL PANEL A'

a<.--l.ea leggy ass~sss asss ss sj aa asa Ov ow lg N ox okv~XR IRI K~9.g)Q)gl~.hL'k<<t s%4 SISSW gg Ct'l aS~sc i>>v 7VQ5 oo~o or.o~o qp qC C~~~pat c.p P~gf Ct~~t~'I.~~I F pe IN IN gO~IIII~pe)J'ANEL P811 SGT AND H2 RECOMBINER PANEL a Ua't a PANEL P812 REACTOR BUILDING Hgsv PANEL+>, asS>v-4R jk~g~~~aat t~etta i4'a t~ap

.

,HAJJ f Sl gg Q CtÃa>>'eee%d'g&Icy ,@~ggt'k e'ee~~I~PANEL P813 CONTAINMENT VENT AND PURGE PANEL

.

• .I PANEL P814 CONTAINMENT MONITORING DISPLAY PANEL ilt t~~k5 5 8~+~~~O$t a 1 mseu me y y~g@QH'-ggQg llQfgg I la a O'ctime t C a l PANEL P821 MAIN STEAM LEAKAGE CONTROL PANEL

PANEL P824 COOLING TOWER CONTROL PANEL PANEL P825 RCC AND SW CONTROL PANEL

~J c y>~'f4'L4 Q QQ~l f4 Q"~sl$kg<<'(.PANEL P826 CONTROL ROOM HVAC PANEv<<D7 pm@OQ+~IF/44ag@c,y iL

.0 H010 Ia II&'k@1 p~>i4II-~5W 5888 REER~~~BE%SD xt'Ka aa4 aha L4 C4 54 L4 II I II WIRIWWWW 0~~d4 W'4 ee eflux R4 k4 C4 R4 8 5 PANEL P827 SGT AND H2 RECOHBINER PANEL~p~t>

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PANEL P832 RFW HEATERS, VENTS AND DRAINS (3 of 4)~bs~eli lpga[ihr V-I BD'T'1 p~~go g%hag j~]1 j j"j Pz I=M

.0 PANEL P832 RFW HEATERS, VENTS AND DRAINS (4 of 4)Igg Cl S~'~9~4Qg f I)rs v~'~e I (I~~~~~~~~g~~~~~'e,~~~~~~~~~~rr~~I4~~~~~~~v~~~~~~Qggg~~r~I't 1 I y>I~~~~~~~~~~r~~~~~~~~~~~~~I,~l~~~~~~~r~~~~~~~~\~r'r'~"J.j..-.--"-'i

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~IMMI It~t%%%%1%'il 4&"Ci'k Ci WCPSSS SS~R~~~~4~~0 0~~4 KR%~ECRU 4+E~~PANEL P001 REMOTE SHUTDOWN RCIG SYSTEM (LEFT SIDE)

PANEL P001 REMOTE SHUTDOHN RHR SYSTEM (RIGHT SIDE) 0, 0

.PANEL P100 REMOTE SHUTDOWN SW SYSTEMS~~lag@n Il II CI V IC CI V Ij CI~I I I@Pl I I V,;PiiP lgllCf CA~i'.C.'hW W"W SC8%SCSI I@PS~Q>'~Qx'Q<Q~'I I 0 ,+%1+0-240.VOI'~~~~C~C 4 0~~~~~~~~~~~0~0~~0~~~~~~~

.

n Rr, Ifb P6<<al 0 PQ'Fn-C26 Oo lI nan Oo Il<<Jp I.Il r I P642 I<<1 0<CONTROL RO Elev.50l 00 Oo nil'D umph:-~IIIImf<<f<<<<f',,~VO@Y DO'PERTURE GARO II<<iA-g 2CCI-PII94 rg I-ff n 9?I!ff iaaf.Comjvtf.r Perinhf ra1s I':.P-'91~nt,<<'nf,"I I I I Q~fJLATf~y naraen5.'"~+QCKK2 PO.g WASHINGTON PU8LIC POWER SUPPLY SYSTEM HANFQRQ NQ.2/2-1/-8/

PANEL TONFIGUITATION YI k l')SI/-'TI IC)I ll 23/30 f>7 g I3 80 27 I Z t't ZE>5'I 2 I'I 2 to I I (t Z3 30 7 I"I Z.I Z.8 I I 15 Z5 I 16>C3 30 AHh 10 17t Et 15 ZZ 2'I 5 I 2 I't Zt ID 1 17]2'I I 31 I'I83 5AM I 7 I!tl[Zl ZI3'1 I I I'5 25 IS 25'5 15'Z 2'f/13 iZO 27 I IO)17 I Z'I 5 I Z.I I 26 t 23'C>04 t NOV 7 I I Zl IZII<ti$18 2$>6 23 3Z)P 832 Pfor)3 I POD I PI 00 Pelt//PB2.7 I-'(3 I Z.PB2 I PBZ>t PP>25 I t)2(P/'INN Lt Iv))CATI)F N'>/I EYvf I'.1':rt 7Z.tuvvf)l F>ETJ PttEPART D P/'e/el>>ED PREPARED Tria Jet KED PREP>at>ED 7!ra 4>t)RD PREPARED VVie/8>>UED PREPARED vive/et.U!>EW NEv>Ew'Ta FNKEE i'>.47>Pi AM..Uau N-v>E>v Kt I i>.W I i D D D P P E tv Tr.v t>E>'iivv vat r,~-Et.-v7 TA K F'Acr I (.L.$$A)TASK FORCE.PRI>)f(fTIZE (f3RR-'(.0.

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