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, Mcgilton C, Van Erem B WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
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ML17276B012	List: ML17276B010 ML17276B013
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NUDOCS 8202020153
Download: ML17276B013 (177)

Text

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

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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 Section Review Plan

~Pa 1

e 2.0 Management and Staffing 2 3.0 Documentation and Document Control 6 4.0 Revi ew Procedure 6 5.0 HED Assessment Procedure 8 6.0 Review Findings 11 6.1 Control Room Panel Arrangement 12 6.2 Control Room Wide Survey Reviews 14 6.2.1 Wor kspace Environment 14 6.2.2 Communications 18 6.2.3 Computer Systems 19 6.2.4 Indicating Light Review 20 6.2.5 Annunciator System Design Review 25 6.3 Control Room Panel Configur ation Reviews 38 6.4 Control Room Enhancement Reviews 40

~ 6.5 Control Room Annunciator Panel Reviews 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 Mile 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

'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.

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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.

Completion of open survey items not reviewable at the present time will be completed as design, construction, and operational readiness allow.

4.2 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.

4.3 System Functional Review and Analysis 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.

4,4 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 of his tasks is being evaluated by; verifying that required control perfor-'ance 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.

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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.

Assess Human Factor Task Force Member I Perform Review Concerns; Develop I Prepare Review Report Recommendations Assess Review Com-pleteness; Assess Task Force Team Review Report Findings Operational Impact; Assess Engineering Impact Assess HED Discrepan-Task Force Team Prepare HED Report cies; Prioritize HED's; Approve HED Corrective Recommendations Assess HED Recommenda-Startup Control Review HED Report tions; Assess Con-Room Coordinator struction/Startup Impact Task Force Team/

Startup Control Resol ve Conf 1 icts Room Coordinator Startup Control Room . Project Directive to the Coordinator AE Architect Engineer Prepare Detail Design (AE) Changes

.0 ~iFi di ~Pa e Section 6.1 Control Room Arrangement 12 Section 5.2 Control Room Wide Survey Reviews 14 6.2.1 Workspace Environment 14 6.2.2 Communications 18 6 '.3 Computer Systems 19 6.2.4 Indicating Lights 20 6.2.5 Annunciator System Oesign 25 Section 6.3 Control Room Panel Configuration Reviews 38 Section 6.4 Control Room Enhancement Reviews 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 Reactor Core Cooling Systems (ECCS)

P602 Benchboard Reactor Water Cleanup and Recirculation Systems I P603 Benchboard Reactor Control Systems P800 Benchboard Electrical Generation and Distribution Systems P820 Benchboard Main Turbine and Miscellaneous Systems P840 Benchboard 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 Off-Gas Control Panel P811 Vertical Panel SGT and H2 Recombiner Panel; Division 11 P812 Vertical Panel Reactor Building H5V Panel P813 Vertical Panel Containment Vent and Purge Pannel P814 Ver tical Panel Containment Monitoring Display Panel P821 Vertical Panel Main Steam Leakage Control Panel P824 Vertical Panel Cooling Tower Control Panel P825 Vertical Panel RCC and SW Control Panel P826 Vertical Panel Control Room HVAC Panel P827 Vertical Panel SGT and H2 Recombiner Panel: Division I P832 Vertical Panel RFW Heaters, Vent and Drain Panel

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Phoo 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)

Benchboard Annunciator Control Zone Oisplay Zone Foot Space - Oepth I Panel Height Specifications Min. Max. Min. Max. Min. -

Max.-I Min. Max. I Min. Max.

o BWR Program ) 30 60 30 68 28 88 o NUREG-0700 26 1/2 (1 27 90 25 90 P601 27 55 35 70 5.38 2 29.38 73 87 P602 27 38 35 70 5.38 2 29.38 73 87 P603 27 38 35-. 70 5.38 2.75 29.38 73 87 P800 27 59 35 73 5.38 3.25 29.38 76 88 P820 27 59 35 73 5.38 2 29.38 76 88 P840 27 59 35 73 5.38 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).

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~~ go.o (rNCVES) 8EiVCHBOARD MEASUREMENTS P60'l, P602, P603, P800, P820, and P840 VERTICAL PANEL ANTHROPOMETRIC MEASUREMENTS IN INCHES I Control Zone Display Zone Annunciator Height Specifications I Min. Max. Min. Max. Min. Max.

I o BHR Program J 42 60 48 68 88 o NUREG-0700 34 70(53)* 41(50)* 70(65)*I 90 P811 26 63 30 71 82 87 P812 30 60 44 72 77 87 P813 30 76 72 79 82 87 P814 72 80 87 P821 23 62 47 71 81 87 P824 30 59 65 72 76 87 P825 37 60 65 71 76 87 P826 33 55 59 66 76 87 26 62 30 7,1 82 87 P827'832 26 78 60 P672 32 58 77 78 85 P851 37 64 53 87 P001 (1) 34 70 76 81 P100 (1) 26 52 53 68 80 84 FCP-1 36 43 84 FCP-2 28 28 30 84 FCP-3 39 45 47 51

• 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 facturerss 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-to design and prepare square headed engravable lenses to replace existing bulb lenses. If feasible, a Task Force recommendation is expected about March 1982.

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WNP-2 CONTROL ROOM INDICATING LIGHT REVIEW PANEL P602 DATE 7-7-81 LIGHT COLOR MEANING REMARKS RRC Lights (1 each) Lighted Indicates "reactor a) Normally not lightec Section above switches vessel low,water level and feed b) Possibly should be S106A and S106B water flow is below minimum" amber color.

(FW pump trip interlocks are sealed in. Tnte interlock reset lock initiates flow control val switches). partial closure.

Lights (1 each) White Lighted-Indicates "low total FW a) Normally not lighted above switches flow and RRC-V-60A(B) is less b) Possibly should be S107A and S107B than 18% open" interlocks are amber color.

(total FW low sealed in. Interlock initiates flow interlock RRC pump transfer to slow spec reset switches),

Lights (1 each) White Lighted-Indicates "main steam a) Normally not lighted above switches line/RRC pump suction low+ T" b) Possibly should be S108A and S108B interlock is sealed in. Inter- amber color.

(main steam lin lock initiates RRC pump trans-pump suction lo fer to slow speed.

+T interlock reset switches.

Lights (1 each) White None-associated with spare a) Switches (SllOA and above switches switch circuit. S110B) and associatei S110A and S110B white lights should (spare switches be removed from pane.

Lights (1 each) White Lighted-Indicates "reactor ves- a) Normally not lighted above switches sel low water level" interlock b) Possibly should be S113A and S113B is sealed in. Interlock initi- amber color (Reactor vessel ates RRC pump transfer to slow c) GE dwg 761E791AD low water level speed. sheet 1 states li@t interlock reset are amber, but sheet switches). 9 'shows 'them as whiti Lights (1 each) Amber ighted-Indicates "flow control a) Normally not lighted above switches alve motion inhibit" interlock b) Should be amber as S109A and S109B is sealed in. presently is, how-(flow control ever, is not con-valve motion in sistent with rest of hibit interlock interlock seal in reset switches. Page 22 lights on panel.

WNP-2 CONTROL ROOM INDICATING LIGHT REVIEW PANEL DATE P602 Jul 7 1981 LIGHT COLOR MEANING REMARKS FEL-1 above White Lighted-Indicates Flux Estima- a) Normally lighted ~

switch S122 tor Bypass Switch is "Normal." b) Possibly should be (Flux Estimator Light goes out when switch is changed to amber Bypass Switch) placed in "Bypass." color and rewired to light when switch is place in bypass.

c) Being added by FDI- ~

TCHI FEL-2 above White Lighted-Indicates "Flux Estima switch S123 tor &sdkaea" alarm is sealed i a) Normally not lighted (Flux Estimator ends Masu4uauce. b) Possibly should be alarm reset amber color switch) c) Being added by FDI-TCHI FEL-3 above White Lighted-Indicates "Flux Estima switch S123 tor Failure" alarm is sealed 1 a) Normally not li (Flux Estimator b) Possibly should alarm reset amber color switch c) Being added by FDI-TCHI White light a- White Lighted-Indicates protective a) Normally lighted bove switch S- relaying lockout reset for LFM b) Being added by PED-213 114A (LFMG moto motor breaker 1B E-2005 breaker 1A con-trol switch)

White light White Lighted-Indicates protective a) Normally lighted above switch relaying lockout reset for b) Being added by PED-S114B (LFMG LFMG motor breaker 1B 218-E-2005 motor breaker'B control switch).

White light a- White Lighted-Indicates protective .a) Normally lighte bave switch relaying lockout reset for RRC b) Being added by P S121A (RRC-P- P-lA breaker. 218-E-2005 pump motor breaker control switch). Page 23

WNP-2 CONTROL ROOM IND'ICATING LIGHT REVIEW PANEL P602 LIGHT COLOR MEANING REMARKS White light a- White Lighted-Indicates protective a) Normally lighted bove switch relaying lockout reset for b) Being added by PED-S121B (RRC-P-1B RRC-P-1B breaker. 218-E-2005 pump motor breaker control switch)

Lights (1 each) White Lighted-Indicates containment a) Normally not lighted above Hyd valve isolation signal closed Hyd. b) To be installed by isolation to isolation valves (Hy-v-17,18, PED-218-E>>5079. PED RRC-V-60A and 19,20 A/B) should be modified to B control switc es 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: 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.

o P820: 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 ECOMMENOATION 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

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.

o P820: 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.

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.

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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 Reactor Core Cooling Systems (ECCS)

P602 Reactor Water Cleanup and Recirculation P603 Reactor Console P800 Electrical Generation and Distribution P820 Main Turbine Systems P840 Reactor Feedwater and Miscellaneous Systems B. Operation Panels - Outside Primary Area P672 Off-Gas System P811 SGT and H2 Recombiner; Division II P812 Reactor Building HEV P813 Containment Vent and Purge P814 Containment Monitoring System P821 Main Steam Leakage Controls P824 Cooling Tower Controls P825 RCC and SW Systems P826'827 Control Room HVAC SGT and H2 Recombiner; Division I P832 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 Panel P851 is heavily conjested hindering operator status review. No summary indication available to operator to identify status of valve isolations.

2. 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. Color legend identification plates are not located on mimic panels for operator reference.

4. Mimics are used only on seven panels.

P840 and P601 do not have arrows indicating direction of flow or energization. For the few arrows that are 3 are backwards. 'sed,

6. 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. 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.

9. 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 abbreviations is not con-sistently applied.

1. REVAB is still used on P601 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.

I 4~ 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).

5. Motor Control Center notation to define power source is not noted on the legend plates. Operators have started placing labeling tape at controls.

1.3.2 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.

- 43-

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

3. 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 '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.

2.1. 2 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.

2.1.3 '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 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.

I 2.2 Recorders 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 corderss P814). Metwell temperature and drywell para-meters are monitored at 2"/hr.

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-have to be slid out of their cases to reach the speed control switch.

2.2.3 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

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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 ~ 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.

b. RCIC turbine and manual steam isolation trips on P601 have the same problem as "a" above.

2. Pushbutton "Containment N2 Backup Valve CIV-V-39B" is mislabled. The control is used for testing the Digital Electric-Hydraulic pumps.

2.4.2 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.

I

2. 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.

- 49-

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 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.

2.5.2 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 Panel alarm numbering is in a row/column sequence using a numeric/numeric scheme.

3.3 ~ 2 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

~Pa e Review Report A-1 HED Report A-5 Pr ioritization Criteria A-6 Letters of Direction 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.

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

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-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 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) 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 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 Rev. 1, 12/8/81

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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 abilityy sequence from left to right. With the addition of mimi-operating cing demarcation lines and a system flow diagram legend plate, oper-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 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-65A RFW-V-32B RFW-V-65B B. Main Steam Line Drain System

1. Rearrange per configuration drawing:

MS-V-20 MS-V-71 MS-V-21 MS-V-72 MS-V-69 MS-V-73 MS-V-156 C. RWCU System

1. Rearrange per configu. ation drawing:

RWCU-V-31 RWCU-V-40 RWCU-V-34 RWCU-V-42 RWCU-V-44 RWCU-V-lA RWCU-V-100 RWCU-V-1B RWCU-V-104 RWCU-V-106 D. RRC System

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 FEL-1 B35-S123 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 Rev. 1, 12/8/81

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~ 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.

Risk Assignment Based on:

Guidance in draft NUREG-1580, 0659 6 0700.

a. High NRC audits of other control rooms.

b. Medium BWR Owner's Group decisions.

c. Minimal Note 3) Schedule to Com lete

-1. Prior to fuel load

2. After fuel load

3. Never

- A s

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WNP-2 HUMAN ENGINEERING DISCREPANCY REPORT Page I of Z P

PANEL P602 RWCU (4.1) REPORT NO. 017 DATE ~~81 DESCRIPTION OP HUMAN ENGINEERING ~ s ~

CATECORY LIS ~ RIS SCHEDULE TO MAN-HOUR DISCREPANCY '..PROPOSED CHANGE; '1)  : (2) 'OMPLETE (3) REQUIRED REMARKS

1) The RWCU systen lacks visibility 1) Rearrange the following IV ENG.

as to flow path or operating sequenc . RWCU control switches per the 40 Specific concerns ares attached configuration draw-ing+ CONST.

a) The RPV vessel re)ect control- 119 ler is separated froa its respective RMCU-V-31 (Itezi 462) valve controls. RWCU-V-34 (Iten 457)

RWCU-P-1A (Itez 450) b) The RMCU system controls are RMCU-P-1B (Item 455) not arranged to facilitate ease of RWCU-V-40 (Itea 456) operation. The two systen bypass RWCU-V&2 (Iten 460) value controls are uot grouped to- RWCU-V-44 (Iten 461)

I gether, the systen suction controls RWCU-V-100 (Iten 458) are reverse of norual convention (Bh RWCU-V-104 (Iten 451)

CO rather than AB) aud control operatin RMCU-V-106 (Iten 453) sequence gunps both vertically aud :

horizontally rather than a suooth sequence frozL left to right.

2) The two RWCU system con- 2) None IV NA 2) This is not considered ductivity, recorders (G33-R601 to he a significant pro-and R603) are reverse of normal blem.

convention (outlet before in- .

let) .

3) Enhancement is inadequate. 3) Add mimic, demarca- NA 3) WPPSS to perform.

tion lines and other en-hancements as defined in Enhancement Guidelines.

~

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.

Risk Assignment Based on:

Guidance in draft NUREG-1580, 0659 & 0700.

a. High NRC audits of other control rooms.

b. Medium BWR Owner's Group decisions.

c. Minimal Note 3) Schedule to Com lete I

1. Prior to fuel load

2. After fuel load

3. Never

- A

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~ ~

~ ~

~ ~

~ ~

~ ~ ~

~

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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.

Risk Assignment Based on:

Guidance in draft NUREG-1580, 0659 & 0700

a. High NRC audits of other control rooms.

b. Medium BWR Owner's Group decisions.

c. Minimal Note 3) Schedule to Com lete I ~

1. Prior to fuel load

2. After fuel load

3. Never

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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 Date: June 30, 1981 ~

9(

H. McGilton-90E TO B. A. Holmberg - Deputy Project Manager, Engineering WNP-2 904A B. Vanerem-926f BA Holmberg-90<

From: R. G. DaValle - Control Room Design Review Coordinator 906D sf(2)

EAF/lb

Subject:

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 Task Force Member Room Review Supply System Operations Control Room Review Task Force Member

- A Wt 102 ERR

o INTERNAL'DISTRIBUTION~~j.,',<;, "r r, qie'" THIS LETTER SATISFIES COMMITMENTNO.

. GK -

Afflerbach 927N-.'-'-""-: . THIS LETTER IDOC ) IDOES NOTI ESTABLISH k IIEW COMICITMENT.

%)XvkHa=A06D=.-.g.-:,- ':, ~ WPPSS CORRESPONDENCE NO.

GJF/lb ..: .

BAH/lb f-(2) .-=

August 31, 1981 MPBR-RO-81-146 Hr. J. A. Forrest f.roject Director ..'=: .-

. RESPONDS TO: N/A Burns 5 Roe, Inc. RESPONSE BY: Sept. 4 REQUESTED 601 Williams Blvd.

WA 99352 'ichland, S ubject: .SUPPLY SYSTEM NUCl.EAR PROJECT NO. Z.

HED REPORTS H13-'P602'

Dear Nr. Forrest:

letter is your authorization to diTect G ~

'his 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, change is uncovered, a copy of the if during the' D pre at a BOP 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 tern:No.

D-O 6 1

-01 018 ~ 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, B. A; Holmberg Deputy Project Nanager, Engineering, WNP-2

~Q BAH/GJF/111 cc: MNP-2 Files - w/attachment n - BP UTHDR: GJ Freeman FDR slGNATURE oF: BA Holmberg FOR APPROVAL OF GK Affler c APPROVED DATE

~ wev 'L

- A ~

Sums and Roe, lric.

601 Williams BlvcL s Richisnd, Washington 99352 s TeL (509) 9434200

Subject:

Work Order 3900 WNP-2 Washington Public Power Supply System Contract No. 2 Control Room Modifications Responds to: NA September 15, 1981 BRGE-2-RO-81-523 Response Req'd By: 9/26/81 General Electric Company Nuclear Energy Division M/C 394 175 Curtner Avenue San Jose, California 95125 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. Holmberg - Supply System - 3 R. G DaValle --Supply System - 1 G. F. Freeman - Supply System - 1 J P. Cooper - Supply System - 1 E. A. Fredenburg Supply System 1 J. Ho M Miller GE Site 1 W. S. Chin - BPA - 1 - A WNP-2 File J H. Ralphs Supply System - 1

0 APPENDIX B TYPICAL ANNUNCIATOR PANEL REVIEW DOCUMENTATION PACKAGE PANEL P602

~Pa e Review Report B-1 HED Report B-15 Prioritization Criteria B-18 Letters of Direction 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 2-

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 Proposed Annunciator Window Color Changes 2~ Proposed Annunciator Window Wording Changes

3. - Annunciators Having Multiple Inputs

4. As Is Annunciator Arrangement (Grouping) 5 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 'Amber to To be consistent with all other "Downscale" Downscale White annunciators which are white.

A5-3. 3 Off Gas High-High Amber to Both the Off Gas "High-High" Radiation and Radiation Red 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 Amber to Both the "High-High" and the "High windows High-High Radia- Red for this parameter are presently amber.

tion This change will also match the light colors on P604.

A5-3. 2 Off Gas Post- Amber to Same as above.

Treatment High- Red

~ Qi High Radiation A5-1. 5 Reactor Building Red to Both the "High-High" and the "High" windows Vent High Radia- Amber for this parameter are presently red.

tion A5-2. 5 Reactor Building Amber to To be consistent with all other "Downscale" Vent Monitors White annunciators which are white.

Downscale A6-5.1 Recirc Drywell Amber to Is an operator information annunciator.

High Press Switc White A In Test A6-3.4 Flow Cont Valve Amber to Is an operator information annunciator.

A Hyd Power Unit White Standby Hyd Pump Operating Page 1 of 2

- B

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 Amber to Is an operator information annunciator.

High Press Switch White B in Test A6-3.8 Flow Cont Valve Amber to Is an operator information annunciator.

B Hyd Power Unit White Standby Hyd Pump Operating A6-6.7 ATWS A or B Test Amber to Is an operator information annunciator.

Switch in Test White A13-2. 2 Reactor Bldg White to For consistency and to conform to GE draw-Floor Drain Sump Amber ing 807E174TC.

Level C002B High-High A13-1. 3 See Attachment 4 White to 'o conform to GE drawing 761E791AD.

A13-2.3 Amber A13-3.3 A13-4.3 A13-1.4 See Attachment 4 White to To conform to GE drawing 761E791AD.

A13-2.4 Amber A13-3.4 A13-4.4 Existing P603 Loss White to Operator warning.

A7-4.8 of 125 VDC A13-6.1'nnunciator Amber Proposed Page 2 of 2, 5-

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 Radwaste Controller 1 Trouble Radwaste Logic Controller 1 Trouble.

A5-1.8

~, Proposed A13-4.2 Existing Radwaste Controller 2 Trouble Radwaste Logic Controller 2 Trouble.

A5-2.8 Proposed A13-5.2 Existing Radwaste Controller 3 Trouble Radwaste Logic Controller 3 Trouble.

A5-3.8 roposed A13-6.2 A6-4.1 ecirc Motor A Lockout Bus Under Volt- Recirc Motor A Breaker Aux. Trip Cir-ge cuit Under Voltage.

A6-4.5 ecirc Motor B Lockout Bus Under Volt- Recirc Motor B Breaker Aux. Trip Cir-ge cuit Under Voltage.

A6-5.5 ecirc Drywe11 High Press Switch In Recirc Drywell High Press Switch B In est Test.

~ - B Page 1 of 1

WNP-2 CONTROL ROOM ANNlJNCIATOR REVIEW Attachment Page 1 of 2 Panel/ Annunciator Meaning Remarks Annunciator P602 Reactor Water Cleanup Pump Actuated by high Cooling Water High Temperature temperature on either RWCU pump.

A5-4.7 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 Meaning Remarks Annunciator Remote Shutdown Transfer Switch Actuated by any 1 P602 In Emergency Position of 20 switches.

A5-l. 6 Recirculation Motor A/B Ikigh Actuated by any 1 P602 Temperature of 12 temp sensors on either pump.

A6-6.6 B

"AS 'X GEHENT

<<.ttachment 4 Page 1 of 3 AtIAllN:IATDAh5 - BOARD P602

< eeurlTng FaTn Stea~ Off Cias Reactor Reactor Denote S <utdown filler Oceln A ad<<as to F loor Area Line Iligh Post Treat<qent Building Vent Building Vent Transfer Switch Inf Iuent Cu>>l col lor I Illgh Aadlatldn III qh-Illgh-II I gh II I gh-IIIgh Illgh In Emergency Conductivity 1< uuhle Aadlat Ion Radlat lon Radl ation Posl t ion Illgh/Low Aadlat lo>> /P g (lew Fuel Hain Stea<<< Reactor Carbon Be<I Reactor Aadwaste Filter Demln Aa<lwas te Storage N.ea L lne Dulldlng Vent Vault Building Vent EFfluent Ef f luent Control ler 2 Ii lgh Honl tors Sample F low Ill gh Honl tors Illgh Conducti vl ty Trouble adiatlon Downscale Illgh/Lnw Radlat ion Downscale Radl a t Ion Illgh/Low Reactor Off Gas Off Gas Dff Gas Off Gas Service Mater Reac Mater Aadwaste Building Post Treatment II I gh-II I gh Vent Pipe Vent Pipe Ef fluent Cleanup Pump Control ler 3 II I gh Illgh-II I gh Radiation IIIgh-II I gh Sample FLow Illgh Flow Trouble Aadlat lon R ad l a t Ion Radl at ion II I gh/I.ow Radiation g Ill gh/Low TUI'bine Off Gas Dff Gas Off Gas Off Gas Reactor Reac Mater SPEAR OUI 1 ding ~

Post Treatment IIIgh Vent Pipe Sample Flow Building CC C1eanup Pump Ill gh Iligh Radl ation Illgh II I gh/Low Mater lllgh Cooling Mater t

I a<i la Ion Radiation IIadlat ion Aadiation. Illgh Temp adwaste Off Gas. AIIR Carbon Bed RIIA Honl tors Service Mater Reac Mater SPARE Dui l ding Post Treatment Vaul t Downscale Or Effluent Honitors Cleanup Pump Illgh Flow Radlat ion Honl tors Inoperative Inoperative Olsch Pressure U7 IIIgh/Low u Radiation /f  ! I I gh/Low 8 Downscale ul Inoperat I ve lO Area Off Gas Off Gas Off Gas Reactor Bul l ding Aadwaste Effluent Cleanup Filter Cleanup F I I ter I adi a t Ion Honl tors Post Treatment Vent Pipe CC Mater Honltors Honi tors Oemin Inlet Honitors Downscale or Honl tors Honl tors Downscale or Downscale or Fa I lure Illgh Temp Inoperative Inopera t I ve v/

I<ownscale ~ Inoperative Downscale Downscale 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. Rcclrc Pmnp A Re circ Re circ PARE 'Reclrc P(nnp 8 Re circ c irc 1r lp Hotor A Hotor 8 'Ir lp Hotor 8 H(ltur 8 ATMS Bearing Ol1 Bearing Oil AlMS Bearing 011 Bearing Ol I In I t lated Illgh Level Low Level ln1 t late(l lligh Level Low I.eve 1 leclrc Pomp A Reclrc Puny A Reclrc Puny A Reclrc Hotor A eclrc Puny 8 Reclrc Pump 8 Reclrc Pump 8 (q'(!Recim Illgh Hotor 8 Seal Cool lng Outer Seal Seal Staging Illgh eal Cooling Outer Seal Seal Staging Mater lllgh Leakage Flow lllgh/Low Vlbrat lon ater lllgh Leakage F low Il1gh/Low Vibration Low Flow .aw Flow /V 8

Icclrc Hutor A Reclrc Hotor A Flow Cont Valve F low Cont Valve Ieclrc Hotar 8 Reclrc Hotor 8 FLow Cont Valve Flow Cont Valve A llyd Power A llyd Power Ilndlng Mind )ng 8 llyd Power 8 Ily(I Power lib(ding Minding l ll(lI a(l t Coolant Unit Startup Unit Standby 4 aolant Coolant- Unit Startup Unit Standby t.(:ok age Low Flow /t( Inhlb I ted Ilyd Pony Operatln Leakage Low Flow lnhlb1 ted llyd Pulnp Opcral lng Ieclrc Hotor A Recirc Hotar A Reclrc Hotor A Flow Cont Valve ecirc Hotor 8 Reclrc Hotor 8 Reclrc Hotor 0 Flow Cant Valve ockout Bus Bkr Trip Overcurrent A llyd Power ockout Bus Bkr Trip Overcurrcnt 8 Ily(l Power Under Voltage Clrcul t Or Ground Unit Control nder Voltage Circ ul t or Ground Unit Control System Abnormal Under Voltage g System Abnormal g 8 Under Voltage g g le circ System A Flow Cont Valve F1ow Cont Valve eclrc System 8 Flow Cont Valve Flow Cont Valve

)rywe1 I High Drywe1 I !Ilgh A Hotlon A Haxlm(nn rywel I Ill gh Orywell lllgh 8 Hot ion 8 Haxlmum Press Switch Pressure lnhlb I ted Open Llml ted Press Switch Pressure lnh lb I ted Opeil L lml ted Interlock ln Test interlock A ln Test y low Cont Valve FLux Haster SPARE low Cont Valve Reclrc ATMS Reclrc System A Servo Input Controller Controller D Servo Input P(nnp/Ho tor Aor 8 Approaching Control Signal Output Signai Output Signal Control S lgnal hor8 Test Switch Auto Flow ill gh Te(np In Test Range L l(nl t Ahno(mal Abnormal Abnormal g Abnbrmal 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 Reclrc Pump A Reclrc Pump 8 Recirc FÃboR Lou Speed Low Speed Hotor A LEAL DRr?rHamp Auto Transfer Auto Transfer Breaker MIGrr-S/ig H CKT Not Avail CKT Not Avalll Trip p

?Cactor Ridg Reactor 01dg Raclrc Pomp Reclrc Pump Re circ I loor Brain Stipe Floor Brain Swy Hotor A Hotor 8 Hotor A I.evel (COA2A) Level (C0020) Auto Transfer Auto Transfer lockout ligh-lligh III gh-illgh lncomp le te inc omp le te Ileactor Bldg SPARE Reclrc Pump Reclrc Pump SPARE Fqulp Ora ln Sump HTR A Auto Trip HLR 8 Auto Trip ligh Level Or Transi'er to Or Transfer to W Low Speed LoM Speed leactor Bldg SPARE Reclrc HG Set A Reclrc HG Set 8 Re circ Equip Orain Sump Protective Protective Hotor 8 Nigh Temp Relay Trip Relay Trip Breaker Ltl lt/ gl Tr lp

, ITIC l~ acre ro Reclrc HG Set A Reclrc HG Set 8 ileclrc 4'44 8 sire< Pl/IZ macro'~8 8 5g~p Inter lack Interlock Hotor 8 rddP 0'~G< Bypass Bypass l.ockout m'~P HIGH I Wct&A LFVFC W

)PCiC To A?C'aC SPARE SPARE SPARE grhP rf/p sf~~ Fzl/

>A?rli~ <E'fv f+Ari /frglr AFuFZ 4i~>

LFuFL

~

>I Hhite A Amber R Red

PROPOSED ARRANGEM )D COLOR PRIORIZATION At ent 5 Pape ) of 3 nlvaO<CInTOA SS - RO~AO P6OS ARM PR))

IC~un 7n g HaTn Stea<<> Of f A<as Aeactor Reactor e<<<ote Shutdown I')nor Area L lne lilgh Post Treatment Oui ldlng Vent Building Vent Transfer Switch lnf luont IIIgh Conductivity SPARE IIIgh A ad la t Ion II I qh-II I gh-ill gh II I gh-IIIgi> ln Ea<ergency II a<liat IUI< Radiation A ad) at Ion A ad l at Ion Position Illgh/Low

<Iew Fuel Hain Stea<I Reactor Carbon Oe<l Reactor Aadwaste FI) ter Oe<<<ln Stnraqu brea L lne Oulldlng Vent Vault Ou) )ding Vent F.f f luent Ef f lueut Hon)tars Sa<<y le Flow Honltors lllgh Conductivity SPARE II lgh Ill gh Ra<I)ation A Oownscale Illgh/Lnw Radla t Ion Oownscale Aad )at ion II)gh/Low Reactor Off Gas Off Gas Off Gas Off Gas Service Mater Aeac Mater Aul 1 ding Post Treat<oent Il I gh-Ill gh Vent Pipe Vent Pipe Ef f Iuent Cleanup Pump SPARE Ill gh II I gh-Ili gh Rad I a t Ion II)gh-IIIgh Sa<<<p le FLaw Illgh Flow IIadlat ion A Radiation ll)gled A A Radiation A lllgh/Low A Aadlat Ion A lllgh/Low Turbine 0)'f Gas Of( Gas Off Gas Off Gas Reactor Reac Mater Reac Water Aul ld)ng II I gh

)ail)at)on A Post Treatment Aadlat Ion A Illgh Radlat lun

~

'llgh A

Vent Pipe Rad1 a t I on A Sample Flow II I gh/I.ow Oulldlng CC Mater lllgh A Radiation. A Cleanup Pu<<<p A Cool lng Mater Illgh Te<<<p (2)W Cleanup Pump B Cooling Water Aadwaste Off Gas RIIA Carbon Bed RIIA Mon) tars Service Mater Reac Mater SVAAL Ou))ding Post Treat<<<ent Ill gh Vaul t Oownscale Or Effluent Honitor Cleanup Pump II I gh Flow Radl at Ion Honl tors inoperative inoperative Olsch Pressure Aadl a t lou III gh/Low Oownscale W W inoperative W Illgh/Low Area Off Gas Off Gas Off Gas Reactor Bu))d)ng Aadwaste fffluen Cleanup F I I ter Cleanup F liter Indi a t )on Honl tors Past Treat<aent Vent Pipe CC Mater Honltors Honitors Oe<p)n inlet Mon I tars Oowuscale or Honl tars Honl tors Oownsca1e or Oownscale or Fa I lure Illgh Te<<

>t Valve Ulndlng Minding A llyd Power h Ilyd Po~er llndlng lllnding 0 Ilyd Po~er ll Ilyil Puwur Coolant Coolant Unit Startup tlnlt Standby W oolant Coolant Ihilt Startup Un I t S t an<lhy I i:.ik age A Low Flow A lnhlb I ted A llyd P<<ny Opera tin Leakage A Low F low A lnhlb I ted A Ilyil I'ump Operat liig (ec I rc Mo to r h Reclrc Motor A Reclrc Hotor A Flow Cont Valve teclrc Motor 8 Reclrc Hotor 8 Reclrc Hotor 0 Fliiw Cont Valve Lockout Ous Okr Trip Overcurrent A llyd Po~er .ockout Bus Okr Trip Overcurrent 0 Hyil Power Under Circ ul t Or Grouiid Unit Control Jnder Voltage Circ ul t or Ground Uii I t Cont ro I Voltage Under Vol tageA A Systeia Abnormal A A Under Voltage A A System hbnoraiaIA le circ System A Flow Cont Valve flow Cont Valve leclrc System 8 Flow Cont Valve Flow Cont Valve trywel I High Orywei I Ill gh A Hot ion A Hax lanan )rywell lligh Orywell Illgh 0 Hot Ion U Hax lmiim press Switch Pressure Inhlb I ted Open L lml ted Press Swl tch Pressure Inh lb I ted Ope>> L linl ted h ln Test W interlock . A A A ln Test W interlock A low Cont Valve FLux Haster Sphllf Flow Cont Valve Rec lrc ATHS Roc lrc Systria h Servo IIII)lit Control le r Controller 0 Servo input pianp/Hotor hor8 hliliruach lug Control Signal Output S lgna I Output Signal Control Signal hor0 Test Switch hutu Flow Ulllolinn I hluionaa I hbnorinal Abnormal lllgh Teinp In fest Range L linl t A A A A A W A W White A Amber R Red ~ o I 'I I ~ ~ ~ ' I ~ ~ ~ I I ' I ~ I ~ ~ I I I I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ I I I ~ ~ ~ I ~ ~ ~ ~ \ ~ ~ ~ ~ ~ ~ ~ ~ I \ ~: ~ ~ ~ ~ ~ ~ I 'I I I I ~ ' ~ ~ ~ o I I ~ f ~ ~ i ~ ~ ~ I I I ~ ~ ~ ~ ~ I ~ \ ' ~ l ~ ' o I I I ~: \ ~ ~ ~ I I: ' ~ ~ ~ ~ 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. Risk Assignment Based on: Guidance .in draft NUREG-1580, 0659 & 070(

a. High NRC audits of other control rooms.

b. Medium BWR Owner's Group decisions.

c. Minimal Note 3) Schedule to Com lete

1. Prior to fuel load

2. After fuel load

3. Never

COD wHT w HT'eac Water Cleanup Reac Water Cleanup Pump A Cooling Water Pump B Cooling Water High Temp 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 Meaning Remarks Annunciator P602 Reactor Water Cleanup Pump Actuated by high Cooling Water High Temperature temperature on, either RWCU pump. A5-4.7 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 Meaning Annunciator Remarks'602 Remote Shutdown Transfer Switch Actuated by any 1 Xn Emergency Position of 20 switches. A5-1.6 P602 Recirculation Motor A/B High Actuated by any 1 Temperature of 12 temp sensors on either pump. A6-6.6 21- "AS ARRANGEHENT HED Report N 6 Ar.tac'nmerit 2 Page 1 of 3 A<lAIAICIATOAAS - BOMB P602 I ter Demln Aadwaste l<<g eeueITrig HaTn Steam Of( 7>as Reactor Reactor Remote Shutdown HF Cu>>l ro I ler I < Id I'oni'rea L ine illgh Post Treatme>>t Building Ve>>t Building Vent Transfer Switch Inf lue>>t illgh Aadiatlon Il I qh-IIIgh-II I gh III gh-II I gh IIIgh In Emergency Cond>>cti vl ty I<'u<dile Aadlatlo>> Aadlat ion Aadlat ion Aadi a t ion Position lllgh/Low /P llew Fuel Hain Stea<<< Reactor Carbon Oed Reactor Aadwaste F liter Oemln Aadwaste Storage h< ea Line Building Vent Vaul t Building Vent Effluent Ef fluent Controller 2 <I lgh Honl tors Sa<qile F low Illgh Honitors lligh Conductivity Troub I e Aad1 at Ion Downscale IIIgh/Lnw Rad la t Ion Downscale Radiation lllgh/Low Reactor Off Cas Off Gas Off Gas Off Gas Service Mater Reac Mater Radwaste Aul Post Treatment Il I gh-ll!gh Vent Pipe Vent Pipe Effluent Cleanup Pump Controller 3 Illgh Illgh-IIIgh t Rad I a I on Iligh-IIIgh Sample FLow IIIgh F'low Trouble II adl at lon Radiation Radl at Ion lllgh/Low Aadla t ion g illgh/Low Tu< blue OI'f Gas Off Cas Off Gas Off Gas Aeactor Reac Mater SrnAE Building Post Treatment Illgh Vent Pipe Sample Flow Building CC Cleanup Pump II lgh Illgh Radiation Illgh III gh/Low Mater lllgh Cooling Mater Iadiatlon Radiation !Iadiatlon /<<'adiation. Iligh Temp adwaste Off Gas RIIA Carbon Bed RIIA Honi tars Service Mater Reac Hater SPARE Bui lding Post Treatment Illgh Vault Downscale Or Effluent Honitors Cleanup Pump Illgh Flow Radiation Honltors Inoperative Inoperative O lsch Pressure Downscale lnoperat I ve lllgh/Low Radiation /f III gh/Low L<l Area Off Gas Off Gas Off Gas Reac tor Building Aadwaste Effluent Cleanup F II ter Clean>>p Filter Radiation Honitors Post Treatment Vent Pipe CC Mater Honitors Honitors Oemln Inlet Honi tors Downscale or Honl tors Honltors Downscale or Downscale or Fa I lure Iligh Temp Downscale Inoperative inoperative Downscale ~ inoperative Downscale H Ifhite A Amber R Red 0 "AS ARRANGEMENT HED Report N A L~e)11(lierlt 2 Page 2 of 3 AIIIIUIICIAIORA6 - 00ARO P602 SI'ARF. Roc)re P(nnp h Re circ Rec)rc PARE Reclrc Pun(p 8 Re circ R((c lrc Hotor A Motor 0 Tr lp Motor 0 Motor 0 Trip Bearing Oil ATWS Bearing 0)1 Bearing Oil ATQS Bearing 0)1 in) t lated Illgh Level Low Level ln I t I a te(l Illgh Level Lnw I.eve) p Ieclrc Pu(np A Recirc Puny A Recirc Pump A Reclrc Hotor A eclrc Puay 8 Reclrc Pump 8 Recirc Pump 8 Rec)rc Motor 0 Seal Cool ing Outer Seal Seal Staging Illgh eal Cooling Outer Seal Seal Staging II)gh Illgh Leakage II)gh/Low V )bra t )on ater Iligh Leakage Floe Illgh/Low Vlhl ation Water I.ow Flow 8 F low .ow Flow H i/ Inc)re Motor h Roc)re Hotor A Flow Cont Valve Flow Cont Valve Iec I rc Ho tor 8 Reclrc Hotor 8 Flow Cont Valve Flow Cont Valve IIIndlng II)nding A Ilyd Power A Ilyd Power Iinding II)nding 0 Ilyd Po~er 0 Ily(l Power C(1(11 an t Coolant Un I t 5 tar tup Unit Sl.andby oolant Coolant Unit Startup Unit Stan(lby L<<ok age Low Flow lnh lb I ted Ilyd Pony Operatin leakage Low Flow lnhlbl ted llyd Pump Operating Iec)rc Hotor A Recirc Hotor A Reclrc Hotor A Flow Cont Valve Iecirc Motor 8 Recirc Hotor 8 Reclrc Hotor 0 Flow Cont Valve ocknut Bus Bkr Trip Overcurrent 'A llyd Power ockout Bus Bkr Trip Overcurrent 0 Ily(l Power lieder Vo itage Circuit Or Ground Unit Contro I nder Voltage Clrcui t or Ground Unit Control System Abnormal Under Voltage g System Abnormal g 8 Under Voltage ~ p Ie circ System A Flow Cont Valve Flow Cont Valve ecirc System 8 Flow Cont Valve Flow Cont Valve Irywe I 1 Illgh Orywel 1 .'I 1gh A Hot)on A Hax )mum rywel I II I gh Orywell lllgh 0 Hot)on 0 Haxlmu(a Press Switclr Pressure lnhib I ted Open Llml ted Press S~itch Pressure lnhib I ted Open Limited Interlock In Test Interlock h In Test y ~ FP low Cont Valve FLux Haster SPARE Flow Cont Valve Rec )re ATIIS Rec )re Systo(a h Servo Input Controller . Controller 0 Servo Input P(nnp/Ho tor hor 8 Approaching Control Signal Output Signal Output Signal Control S igna1 Aor8 Test Switch hi(to F low Abnormal Abnormal Abnormal Abnormal II I gh Te(np In Test Range L)ml t W White A Amber R Red "AS RRANGCHENT HED Report No. At tac.Imert 2 Page 3 of 3 ANNIINCIATOR A)3 - BOARD P602 ,rrrrc4t g'r Dg Recirc Pump A Reclrc Pump 8 R eel rc glOaN Dr2rIirr Low Speed Low Speed Hotor A S'u~W Auto Transfer Auto Transfer Breaker - irir,l/ <Fur-'y/Grr llot Avail CKl'ot Avail ~ Trip CKT p Reactor II ldg Reactor Bldg Rocirc Pump Reclrc Pump Recirc I'loor Brain Sump Floor Drain Suay Hotor A Hotor 8 Hotor A l.eve 1 (C002A) Level (C0020) Auto Transfer AiIto Transfer Lockout II igh-Ill gh Illgh-Ill gh lncomp le te incomplete IIeactor Bldg SPARE Reclrc Pump Recirc Pump SPARE Fqulp Drain Sump HTR A Auto 1'rip HN 8 Auto Trip Iligh Level Or Trans('er to Or Transfer to W Low Speed Low Speed Ieactor Bldg SPARE Reclrc HG Set A Reclrc HG Set 8 Recirc Equip Drain SImy Protective Protective . Hotor 8 Iligh Temp Relay Trip Relay Trip Breaker Nl lII gl Trip . /.rc ry Werc ro Reclrc HG Set A Recirc HG Set 8 ilecirc interlock interlock Motor 8 )PION 8'ir~~ Orris B Sg~ Fenrir ri'~G~ Bypass Bypass Lockout rrrrI P dicrI r f vs W 6 C'gZl-A?c'rc Eddic ro SPARE SPARE SPARE /Prrà 8/p 5ffgn WuR8i~F rg'i~re rr rg'rr l,ggF<A'P+gp gF'vrZ /id+ LFvFr- lr ~ >J Hhite A Amber R Red ~ o 0 PROPOSED ARR~"~PV >~ "O'..OR PRIORITIZATION HED Report No 'age 1 of 3 AAAIIACIATWhs - DOAAO P6OP Iti~!iic ing Ofr Gas Aeactor Reactor emote Shutdown Fl tcr Ocmln f lnor Area L lne II I gli post Treatment Oui ldlng Veiit Building Vent Transfer Switch Inf luent II I gli Aad la t Ion II I qh-II I gh-II I gh Illgh-IIIgh IIIgh In Emergency Conduct I v I ty SPARE Aailiatioii A Aadlat ion A ad I a t Ion Aadl at ion Posl t ion lllgh/Low R flew fuel Hain Steam Reactor Carbon Deil Reactor Aadwaste Filter Ocmln Storagr Area L lne Oui 1 ding Vent Vaul t Building Vent F ff luent Ef fluent Honl tors Conductivity SPARE II igli Honl tors Samp le F low Ill gh Ill gh Aa<liat ion A Oownscale Illgli/Low Aadl a t Ion. Oow>sca le Aadlat lon Iligh/Low Reactor Off Gas Off Gas Off Gas Off Gas Service Mater Aeac Mater Dul ldlug Post Treatment III gh-II I gh Vent Pipe Vent Pipe E f f luent Cleanup Pump SPARE II I gh II I gh-III gh Radiation IIIgh-II I gh Sample FLow IIIgh F low Dad l at lou Radiation A A Raiilat lon A II I gh/Low A Aadlat lon A Illgh/Low M Iurb lne Off Gas Off Gas Off Gas Off Gas Reactor Reac Mater Reac Mater llu I I ding Post Treatment illgh Vent Pipe Sample Flow Oulldlng CC Cleanup Pump A Cleanup Pump B II lgh l ail la t I on A Iadwaste lllgh Aadlat Ion Off Gas A Radiation AIIA A Ill gh Radiation Carbon Bed A II igh/Low RIIA Honl tors Mater lllgh A Radiation. Service Mater A Cool lng Mater lllgh Tscp (2)M Reac llater Effluent Honitor Cleanup Pump Cooling Water qh Zeus SPARE ~ Dul lding Post Treatment Ill gh Vault Downscale Or IIIgh Flow Radlat lon Honl tors inoperative lnopera t I ve 0 I sch Pressure Radiation A II I gh/Low A A Oownsca le lnoperat I ve M Illgh/l.ow Area Off Gas Off Gas Off Gas Reactor Bui1dlng Aadwaste Effluen Cleanup Filter CIeanilp F liter Andi a t Ion Honl tors post Treatment Vent Pipe CC Mater Honltors Honl tors Oemin Inlet Non I Lors Downscale or Honltors Honl tors Oownscale or Downscale or Failure lllgh Temp llownsca le W Inoperative M Oow~sca le M Oownscale inoperative M inoperative M M Notes: (1) Relocated to annunciator A13-P602 (2) Existing annunciator A5-4.7 split into two (2) annunciators. W White A Amber R Red 0 PROPOSED ARRANGEH 0 COLOR PRIORITIZATION IIED Report No Attachment 3 Page  ? of 3 AIIIIIIIICIATOAAI> - AOAAO r602 Radwaste Recirc. Reactor Bldg Aeclrc Aecirc Aec lrc Pump A Pump 0 Floor Drain SPARE Lou Speed Lou Speed Hotor A Sump Level Auto Transfer A Auto Transfer A Breaker ~ (C003) High- CKT riot Avail(4 CKT Hot Avail(4 Trip R I.g Itcaftor i g Aeactor Bldg Acclrc Pump Aeclrc Pump Aeclrc I loor IIrain Sump Floor Oraln Swy Hotor A Hotor 0 Hotor A I eve l (COI)2A) Level (C0020) Auto Transfer Auto lrausfer Lockout II igh-Illgh Illgh-Illgh A lucomp le te A(4) Incomp le te A(4) lIcactor Illdg SPAAE Aeclrc Pump Aecirc Pump SPARE (4lulp Ora In Sump HTA A Auto Trip HIA 0 Auto Trip II lgh Levc I Or Transfer to Or Transfer to LOH Speed LOH Speed W A(4) A(4) tcactul Bldg Radwaste Con Aeclrc HG Set A HG Set 0 Ae circ LqulP Brain S<m~P troller 1 Protective Relay Trip A4'eclrcProtective Relay Trip Hotor 0 Breaker Trouble Trip W A 4 R SPARE Radwaste Aeclrc HG Set A Reclrc HG Set 0 Rec1rc Interlock Interlock Hotor 0 Controller 2 Bypass Bypass Lockout W 2 Trouble 2 3 A A Annunciator SPARE SPARE SPAAE Loss of 125 Controller 3 VDC Trouble A (5) (2) W (2) (3 Notes: (1) Currently in window 1.1. GE drawing 807E174TC Rev. 9 specifies window 1.2. GE Drawing should be corrected. (2) Existing annunciator relocated to F601, see P601 annunciator review for specific location. (3) Relocated from annunciator A5-P602. (4) Windows are currently white. GE drawing 761E791AD specifies amber'. (5) Relocated from P603 annunciator A7-4.8. W White A Amber R Red o - ~ PROPOSED ARRAN(xEMF D COLOR PRlORlTIZATION HED Report No. At chment 3  :-age: of 3 htlldlflclhlOR A6 - BOARD P602 Recirc A Recirc B Sl AOC Rrclrc P<<aa II h Rect rc Recirc. Motor PAIIE Reclrc P<<anp 0 Re circ Recirc Motor B Ir ip Hotar A Tr lp Hutor 0 ATMS Rearing Ol 1 A Bearing Oil ATIIS Dear log Oil Bearing Oil Lo ln I t lated II I gh A,eyr.l Lov Level A In I t I ate<i ill gh /eve I Level A A leclrc Puny A Dec lrc Puny A Rcclrc Pump A Reclrc Hator A leclrc Puay 8 Reclrc Pump 8 Reclrc Puny 8 Rcclrc Hotor 0 Soa I Cool lng Outer Seal Seal Staging II I gh eal Cooling Outer Seal Seal Staglllg II I gh Mater High Leakage F low ll1gh/low Vlbra t lon later Illgh Leakage Flow Iilgh/Low VII)rat lon I <<<<w F low A A A A ow Flow A A A A I<<.cl<<.c Hutor h Rcclrc Hotor A Flow Coot Valve Flow Cont Valve: leclrc Hotor 0 Reclrc Hotor 8 FLaw Cont Valve I'l<<<<w Co<<<<t Valve Il lading Minding A llyd Po~er h Ilyd Power l lndlng lllnd lng D llyd Power 0 Hy<<l Power I <<1<<<< I J<<l t Coolant Unit Startup Unit Standby W ool ant Coolant Dolt Startup U<<1 I t 6 t a<<IIII<<y I <<.<<k a<<je A Low Flow A lnhlb I ted A llyd Pony Operatln leakage A Low F low A Inhib I ted A Uy<<l I'ump Opcrat log (eclrc Hotor h Reclrc Hotor A Reclrc Hotor A Flow Cant Valve teclrc abator 8 Reclrc Hotor 8 Reclrc Hotar D Fl<<<<w Cont Valve Lncknut Ous Okr Trip Overcurrent h Ilyd Po~er ockout Bus Okr Trip Overcurrcnt 0 Ily<<I P<<lwcl Ih<<der Voltage C lrcul t Or Ground Unit Control lnder Vol tage Circ ul t or Ground Unit Control Under Vol tageA A Syste<<a Abnormal 'A A Under Voltage A A System hhoor<<nay Ic circ System A Flow Cont Valve Flow Cont Valve leclrc System 8 Flow Cont Valve Flow Cont Valve Irywe I I Iligh Drywell lligh A Hot lan A Hax l<<aum rywe1 1 II I gh Orywell lllgh 0 Hotlon 0 Haxlmom I Iess Switch Pressure Inhlb I tcd Open Ll<<al ted Press Switch Pressure Inhlb I ted Ol<<co L lml ted h ln Test W Interlock A A ln Test W Interlock A 'low Cont Valve FLux Haster SPIC Flow Cont Valve Rec lrc ATII5 Rccirc Systrm 4 Servo I<<yot Controller Controller 0 Servo Input Pmap/Hat or harB hp))roaching Control Signal Output Signal Output Signal Control Signal Acr 0 Test Switch Auto Flow V<<oo nna I hbnor<<aa1 hbnorma I illgh Te<<ap ln Test Range Ll<<alt A Aboor<<aa I A A A A W White A Amber R Red ~ o F-81-9694 I NTL.ROFFICE MEf~IORAND0 M Distribution: 0 EDC WNP-1 /4 %'ASHINGTON PUBLIC PO>VER SUPPLY SYSTEM Kl EDC INPUT CI EDC WNP4J5 CI Admin File Dater November 2, 1981 L Carey - 9179 WP Gilles - 906D Tot GJ Freeman, Control Room Program Manager CH McGilton - 906D 8 Van Erem - 926 From: RG DaValle, Control Room Design Review Coordinator EAF/LB ~ .RGD/LB

Subject:

HUMAN ENGINEERING CHANGES sf (2)

P602 - ANNUNCIATOR SYSTEM PANELS 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 System Operations Control Room Review

'pply Task Force Member 8 wp loa Ra

~ s APPENOIX C WNP CONTROL ROOM PICTURES

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PANEL P601 ECCS SYSTEMS (RIGHT SIDE)

PANEL P602 REACTOR WATER CLEANUP AND RECIRCULATION SYSTEMS

PANEL P603 REACTOR CONTROL SYSTEMS

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'>>5-. >> ->> ~ M t - -" >>t, - ' 5 - '"5 4' l>>'>>-C~+~~ H>W'5 *'>>">>>>Qi>> .tI~5i-'>>t5t t5t>> . 5 5+>>>> 5w" )3 6 M~xW ~C ") v5 PC 5>>C~ ' .>>t t'>> Y-5"' PANEL P672 OFF-GAS CONTROL PANEL A ea a <.-- l. leggy ass ~ sss asss ss sj aa asa Ov ow K~9. g) Q) gl hL'k <<t SISSW gg Ct lg N ox okv ~. s %4 'l ~ XR IRI C c. ~~~pat p P i>> v 7VQ5 oo ~o ~ ~ gf Ct t~ 'I .~ ~ I ~sc aS or. o~o F qp qC pe IN IN ~ IIII ~pe )J + >, asS > v gO -4R jk~g~ 'ANEL PANEL P812 REACTOR BUILDING Hgsv P811 SGT AND H2 PANEL RECOMBINER PANEL a Ua 't t~ ~~aat a t~ ap'a etta i4 ,HAJJ Sl f gg CtÃa >>'eee Q %d'g &Icy ,@ ~ggt 'k e'ee I ~ ~ ~ PANEL P813 CONTAINMENT VENT AND PURGE PANEL I PANEL P814 CONTAINMENT MONITORING DISPLAY PANEL ilt ~k5 5 8 ~ + t~ ~ ~ ~ O $t a C mseu me y~ a g@QH'-ggQg y l llQfgg I la a O' ctime t 1 PANEL P821 MAIN STEAM LEAKAGE CONTROL PANEL PANEL P824 COOLING TOWER CONTROL PANEL PANEL P825 RCC AND SW CONTROL PANEL ~J c pm@ f4'L4 Q OQ IF/ +~ ~ ' y> QQ <<D7 ~l f4 Q"~ sl $ kg 44ag @ '(. c,y PANEL P826 CONTROL ROOM HVAC PANE v iL 0 H010 SD xt'Ka aa4 aha II L4 C4 54 L4 WIRIWWWW Ia II & 'k@1 I II p~> i4II-0 ~ ~ d4 W'4 ~ 5W 5888 REER ee eflux ~ ~ R4 k4 C4 R4 8 5 ~ BE% PANEL P827 SGT AND H2 RECOHBINER PANEL ~ p~t> >4'4 ~~c~~>~,'4 Pl ~~ ~Za fll V)~~ foal ~lb omuH CO Kl ~ C7 Vl R7 ~~. 'I I 'II I lh I IIIII ~ y ~ "~ ~ I 1 ~ I j'D'T'. = T,< ~y mL aey W r I j P PjgP age y JI hei I¹)N 'j . jj f j jf(f .. 'f Jf PANEL P832 RFW HEATERS, VENTS AND DRAINS (3 of 4) ~ bs ~eli ihr V- I lpga[ go g %hag j j"j j~] ~ ~ 1 BD'T'1 p Pz I=M 0 PANEL P832 RFW HEATERS, VENTS AND DRAINS (4 of 4) Cl Igg S ~ ' ~9~4Qg f v ' I ~ )rsI ~ I ~ ~ ~ ~e ~ ( ~ ~ ~ g ~ ~ ~ ~ ~ 'e, ~ ~ ~ ~ ~ I4 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ rr v ~ ~ ~ ~ ~ ~ ~ ~ Qggg ~ ~ r ~ I 't 1 I y > I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ r ~ ~ l ~ ~ I, ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ \ ~ r ~ r 'r' ~ "J .j ..-.--"-'i ~ ~ ~ ~ ~ ~ va WW rZv ~ ~ r ~ ~ r ~ yt~'t ] t~l .I -~ vg ~ tr v "4nv -'- ~ ~ ~ gt ~ IMMIIt ~t 1 %'il 4&" Ci 'k Ci W CP SSS 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 . 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(9 i t(EPARE FlEC) '(Ecu-ROD Pfor)3 PttEPART D P/'e/el (C) SUPPLY 5'YSTEI>/I / PPROY/qL F>ETJ I Ii POD I >>ED PREPARED Tria Jet (07 IREE cHI NEE TD I3<R slTE. (Et,u.uip) TSET)E CIIAAIC F I'0 C .E I(E) - vt>uu u c PI 00 KED PREP>at>ED 7!ra 4> Pelt// PB2.7 >vt vf tli wr D r riN(it R ht LvvK utUL ivN >FLH>' I-'(3 I Z. D i N I'AKI> i N, A(THAC UJ>Rt>U(, )CONF> NJ>UAI >QN a>i0 Tpt ...,.. ~ Nuittk>(FIN:., Art.ik D tr'TTE>v i>PEFU- J Ei 2>t. D PB2 I t)RD PREPARED VVie/8> P PBZ>t PP>25 I >UED PREPARED vive/et P t)2(P tv E /'INN Lt Iv))CATI)F N'>/I EYvf 'Ta .U FNKEE >Pi AM .. Uau it ,." I ~t'F IAN(FE TO (DE Ck I ir,' i' >.47 ISSUI i<(P t 'I I R Ill- C>VANDI TO IVER 1ITE (E Tr .v t>E>'iivv vat CHiilqi:; 1':rt  !>EW r,~ q3) I ~f)F li'r F 'O C I '. 7Z. (4') .SS>if Hl- ( >tANUF 0" tv SITE NEv>Ew tuvvf) l N-v>E>v Et.- v7 Kt I i>.W TA F 'Acr K I (. L. 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>P TE. t)UAL F)LA>/tthl (AMUP, ST LAtvtvk)IL j7 Pf(EI'At(E Et<)i SITE < (v 5 rt>Ah>I)FA(T I)RE% I k, >ft f(IIATIVE IIED 5,5 APPT(OVAL (IF ucqp) 1 tu.t KO ) tt(l u 1 1 >L. 71 "i>E tv >P tr vt P tr ATIJS I t/ -6/>i I ",Bfil.l S h; it,>US t BURNS AND ROE, INC. iR >C ")IKIUS R >Ut)E ,E RERAL F.t Er Tktr ENGINEERS ANO CONSTRUCTORS r 'it 'Lar i tt'i': ORADELL, N. J. HEMPSTEAD, N. Y. LOS ANGELES. CALIF. Cr; i lt >i'.3:1 ii,t,iah 'N( Fhi "ii. c ~ '+>Uc't> Rf', )ILA(QA (JFFICE

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.'itL L' tit r F I( Ni APERTURE 1 N i>NEE hiNiu AP>'hOVAL riiir STONE .. F>. PT I:ONt I;BI 4'l'i;)Vi DI.";I'=,ll RL-Vjj-'A U 1 I ri. t>AL ii 1"LE ULE KL7( t(HF ~ I)IVtS)t)tlj tutti> FM aura TIME LlOW vt!Tr)ISEk '>3!Q CARD DAT I //F vtav 5>'ANS>lid END IN I LR 5 >AN k t(EN') At.t i"17V EN ik WASHINGTON PUBLIC POWER SUPPLY SYSTEM S>JPV>V I EVEL LAIC: n/e 7 et HANFORD No. 2 it< F(t NNF TFr ",4 ET > t)E 2. g ZD E 0 2. U7>s f z~ p I)OPQTT>ettt) ---' iCIEET FILE )U 1GI)LAUI ' f'IBP. GFI 3HM 5LlI RHh OCT 30 4 i 1 (8 25 Et t5 ZQ 't II I P) 5 8 15 2Z 2'1 IZ i't ZE) 5 lZ. I9 2k 9 t(v 23 30 7 tef 'Z I 28 tf Il 1 ft 25 I 13 ZO '27 (0 lit ZS ZZ 5 12 '9 2( IO '1'I 2"I I 3( 7 I'f ?t 2S 7C 15 22 Z9 10 17 7 I 't 2'f' If ff tf( 25 9 IG 23 Ett'tE RbE N C. Y PRCI E IJF/E I UIQE:LINC& OF INE. R6-1.97 INSTR lAENTATION g VK(eV LDCATII)Ft F(FLE Dtv .)2. PhhttLS C)E ttva EKs TNSTIhitiv)IEN ATIOI)f  ! I-5II(. CO'NFI( IIRATIOt( ! ON(KGL EL ARRAFJC Eh'If:NT li 'Al'vltvGI) (IL ' . )vo t e Nf e'f)Nfit(v!hid[(Oht I(IT(V> h(P (7IQASO t."Atvlft. Ei'1>t&,l'9(LLCP i NT 'hi.'. t)I.L I '.)ANI)ALi 1:Y iii: i: TeASK FL Iv(i. i ieii'-h L ) )KFLPntt E Ktf)A)v)C I tv"tght T t(A tve DA Ai't)R"VAI Vtit-rt(et pL(ii I t(. Apt te .)VAL

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Rf PAKF P824 PIG AFAR,C,V/hL I I

PREPARE PEZg PKG > 5 A t fvOVAL + F PAKF F E .. L PK( I f'REPAEE Pf)32 I Kii, 5 5 AF' et ee FREPARE PI)72 PK(* L P/KNELL'PPROVA FREfARE FNItAt(LE,ENT f'ACKA( F 5 F(vR TNRR PA)v LL S 7 uLI' 'Ll(Llew:e'ii.iee',',F' tv rv kf I,vl Ll)DLE ~Et' (SVi R Ot)INERS GPQIIP '/ t e iASK 1()R(L PRI))KIl Itf-1 (AV, FORCL I'KILR111 E. f.; OL CHAn, PR ebfvhtA )IAKOWAILE 1%%PAP.E, 155!IE IDOL tvAIA HA)COWARE  ! Fte L. PARE / C,,tv(P,() 1. RIIOtvh FLOOR AVO'Jl Per VIEW tif. L) ro OIR (HA)t'AL ',tip .-v: et~0 Ieev e.OIV)PLEIF (- 1)P( RATO R, ev Ifv)I'LITF R I E'v iuVV L I<A)L N! ES l ieANFL> R Pg N1 E k5 1NS(ALL f 5. the,te, (55t )C 5 r Lt)A)e(GES 10 Si'A t 1 </ FGF i(,N (CIIIPLETE v(.f FV I-'.Os Y 5, E No F Y Beth '- 1T'rti ti(L ' SiiE ()L(i F Lt)KIIVII,tiltAT iie N !

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