ML20114D425
| ML20114D425 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/10/1985 |
| From: | CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | |
| Shared Package | |
| ML20114D418 | List: |
| References | |
| NUDOCS 8501310299 | |
| Download: ML20114D425 (90) | |
Text
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O PERRY NUCLEAR POWER PLANT i
DETAILED CONTROL ROOM DESIGN REVIEW
SUMMARY
R$ PORT a
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Prepared for h The Nuclear Regulatory Commission Cleveland Electric illuminating Company gn#aMh
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TABLE OF CONTENTS P.agg 1.0 Introduction 1 l
2.0 Methodology 2 2.1 Review Program Plan 2 2.2 Description of Control Room 5 2.3 Review Processes 5 2.4 Assessment and Selection of Design Improvements 17 2.5 Verification 22 2.6 Management and Staffing 23
.2.7 Data Management 25 2.8 Design Integration 26 O
- 3.0 Review Findings 29 3.1 Assessment Screening 29 3.2 Major Assessment Findings 30
-3.3 Verification Findings 50 4.0 Implementation 81 5.0 On Going Human Factors Program 84 6.0 Conclusion 85 O
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_L_IST OF FIGURES
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Figure Description Page If ' _
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1 .PNPP DCRDR Program Plan. 4 4
jl 2 Integrated Assessment Methodology .21
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. LIST OF TABLES
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Table N M.s. Description
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42-l' PNPP DCRDR Multidisciplinary Team- '28
, .,gy 3-1~ Summary of Control Room Workspace HED's 52 4 . *3 - 2 Summary of Control Room Communications HED's 53
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- 7 p ? S-3 Summary of Contrcl Room ~ Annunciator HED's 54 m_ . . w.
g ~ 41:~ ' Summary of Control Room Labels and Location 56'
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Aids HED'.4
~ Summary of Generic _ Control,-Display-and Panel '60
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. j4 M .- . Layout HED's- ,
s-igyn[4 ~ 3 - 6.- . Summary of' Unit Control Console-(P680) HED's' 611 Summary.cf ECCS Benchboard (P601).HEDs ff N >
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Summary 'of ' Diesel Generator.Benchboard (P877) 62' 63
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'HED's
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-9d, 4 .3-9 ' Summary of Long Response-Benchboard-(P870)'HED's t64-
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- @N 3-10? iSummary.of, Process' Computer and ERIS HED's 65
~3 11' . Summary of Backpanel HED's 66 68-
- 3-125 Summary ofiRemote Shutdown' Panel HED's
- 3-13 .HED Assessment' Listing 69-
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HED Verification Listing -
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h ,: ;hs # [r.4-1T HED Correction Schedule..- Prior.to Start-up.
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Aftero. First Refuel
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<a LIST OF ATTACHME ES
(~)-- Attachment Description A BWROG CRDR Program - Development and Methodology B BWROG Human Factors Engineering - Control Room Survey C BWROG Human Factors Engineering - Control Room Survey Supplement
, D BWROG Human Factors Design Review Of The Perry Control Room - Summary Report E- PNPP Detailed Control Room Design Review Findings F PNPP DCRDR Task Analysis Procedure
.G Task Identification Sheets H PNPP Task Analysis Data Sheets I Human Engineering Deficiency (NED) Report Sheets J " Disagree" and Duplicate NRC In progress Audit
. . Findings K Description of Control Room
- p. L DCRDR Review Team Resumes, Tasks and Levels of Effort M Verification Procedure N PNPP Human Factors Control Room Standards O PNPP Human Factors Design Evaluation f .-+ -e'--py -
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1.0 INTRODUCTION
- O The Perry Nuclear Power Plant Unit 1 is a 3579 megawatt facility operated by
- the Cleveland. Electric Illuminating Company. The unit incorporates a General
! Electric Boiling Water Reactor (BWR/6) with a Mark III containment. A control room of the GE Power Generation Control Complex (Advanced Control Room) design
[ is used to control the power plant. This report documents the work and findings of the Perry Human Factors Program over the past four years. ,
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The Perry Human Factors Program was developed in response to concerns raised j following the Three Mile Island accident that-deficiencias in the human
- - factors design of the Three Mile Island control room may have contributed to j the severity of that accident. This program addresses the requirements of
, >NUREG-0737 Supplement 1. The program includes human factors surveys of L
i~ control room panels, questionnaires and interviews of operators, task analyses of emergency operating procedures relative to the control room and an ongoing
- human factors program which encourages operators and other plant personnel to submit human factors concerns to the Perry Human Factors Unit for review.
p This summary report is submitted to the US Nuclear Regulatory Commission in order to document the work and findings of the Perry Human Factors Program.
Section 2 provides a detailed description of the methodology employed in
.per forming t e h Perry Detailed Control Room Design Review (DCRDR).- Included in this description.is the development of a program plan, conduct of the various
$ ' review processes, assessment of review findings, selection ofidesign improve-ments and verification that the selected improvements correct the deficiencies k without creating new problems. Section 3 provides a synopsis of the major findings from the assessment, a summary of selected design ' improvements and g findings from the verification process. Section 4; discusses the imple-mentation schedule for the design improvements. .Section 5 discusses the PNPP
! . On Going Human Factors Program. Section 6 presents the conclusion of the DCRDR.
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I 2.0 METHODOLOGY
~2.1 REVIEW PROGRAM PIAN
-The Perry Detailed Control Room Design Review (DCRDR) Program Plan addresses and exceeds the requirements set forth in Supplement 1 of NUREG 0737. This has been documented in several submittals to the NRC and will be explained in
. v detail in the following sections of this report.
9 j- The scope of the Perry DCRDR Program Plan is illustrated in Figure 1 and includes the following major processes for identification and correction of Control Room Human Engineering Deficiencies (NED's):
o Establishment of a qualified multidisciplinary team.
o Task Analysis to identify control room operator tasks, information
& control requirements and specific characteristics, and operator response and panel information & controls necessary to carry out the Plant Emergency Instructions (PEI's) and the-Shutdown From Outside
-( }.
The Control Room Integrated Operating Instruction (IOI-11).
t o Availability and suitability of the PEI and remote shutdown instruc-
- tion information & control requirements and specific characteris-tics.
o Control Room Survey.
o Operator Survey.
o Assessment of Human Engineering Discrepancies and Human Engineering Observations to determine which are significant and should be corrected.
o Selection and implementation of corrections and improvements for Human Engineering Deficiencies (HED's).
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j o Verification that selected design improvements will provide the necessary correction and will not introduce new HED's.
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o Coordination of HED improvements with improvements resulting from other NUREG 0737 Supplement 1 Programs such as R.G. 1.97, SPDS and Plant Emergency Procedures; and NUREG 1000.
o Development of an Ongoing Human Factors Program for the life of the plant.
The Program Plan addresses six phases of activity to accomplish the major tasks identified above: Planning, Review, Assessment and Selection of Design Improvements, Verification, Implementation, and Reporting.
The BWROG Control Room Survey Program addresses the Planning and Review phases. The Assessment and Selection of Design Improvements, Verification, Implementation and Reporting phases,were developed and performed by the PNPP Human Factors Multidisciplinary Team.
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O PNPP DCRDR PROGRAM PLAN
[s, PNPP HUMAN FACTORS ""'
TASK FORCE II PLANNING If M ULTI-DISCIPLINARY
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REVIEW TEAM
'I REVIEW PROCESS n
Y ONGOING CON ROL OPERATOR TASK HUMAN FACTORS ROOM PROGRAM SURVEY y u 4 U t
HUMAN ENGINEERING DISCREPANCIES AND OBSERVATIONS U
ASSESSMENT &
SELECTION OF DESIGN IMPROVEMENTS U
IMPLEMENTATION C VERIFICATION
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OPERATOR
SUMMARY
TR AININ G REPORT FIGURE 1
2.2 DESCRIPTION
OF C0KTROL ROOM f
The PNPP DCRDR addresses the Unit 1 control room, common panels used to support Unit 1 operation and the remote shutdown panels. Attachment K con-tains a list of the control room panels reviewed by number and description, a layout drawing of the Unit 1 Control Room, and a Master Parts List Index showing system number and description.
i 2.3 REVIEW PROCESSES The scope of the Perry DCRDR Program Plan utilizes four major methods for identification of Human Engineering Discrepancies and Observations in the control room.
'1. Control Room Survey.
- 2. Operator Survey.
- 3. Task Analysis.
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4.- Ongoing Human Factors Program.
l The following subsections describe the objcctive,' methodology, procedure, review team, and documentation associated-with each review method.
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- 2.3.1 CONTROL ROOM SURVEY The Control Room Survey portion of the DCRDR consists of three separate-surveys
- -BWROG Control Room Survey, BWROG Supplemental Survey, and NRC In-Progress Audit.
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BWROG CONTROL ROOM SURVEY O
The BWROG Control Room Survey was performed from September 21 to 25, 1981 in accordance with the BWROG Control Room Survey Program.
Objective: The objective of the Control Room Survey is to review and assess the adequacy of the arrangement and identification of L.aportant con-trols and displays, the usefulness of audio and visual alarm systems, plant status information provided, procedures and training with respect to limita-tions of existing instrumentation, information recording and recall capabil-ity, the control room layout and environment, and other areas of human factor engineering that potent.ially impact operator effectiveness. The ultimate objective is to identify potential modifications of the operator-control room interface which will reduce the potential for human error.
Methodology: The BWROG Methodology for performing a Control Room Survey was utilized. Details of the BWROG Development and Methodology are included in Attachment A.
Procedure: The Control Room Survey was conducted by the survey team using 4
the checklists shown in Attachment B, Section 3. Checklists for panel layout and design, instrumentation and hardware and annunciators were completed for each panel in the control room and division 1 remote shutdown room, including back panels, auxiliary panels and peripheral equipment that contained controls and displays operated or monitored by the control room operator. A list, description and locations of the panels reviewed is contained in Attachment K.
A checklist for computers was performed for the process computer. Checklists-for procedures, control room environment, maintenance and surveillance, and training and manning were completed only once since they are applicable to the entire control room.
Each specific question was evaluated by the team members generally working in pairs.. The relative degree of compliance was indicated by circling the applicable number. Following the number indicating the degree of compliance is a predetermined number ranging from one to three which indicates the islative importance of the checklist item with respect to the potential for
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operator error. The product of the degree of compliance times the potential for operator error is the evaluation product which is used as a preliminary prioritization. The evaluator provides comments and photo documentation where necessary. Further detai1E of the Control Room Survey Procedure are included in Attachment B, Section 3.
Review Team: The Control Room Survey Team was comprised of the PNPP Human Factors Unit, two BWROG utility members, two human factors specialists and a General Electric operations engineer.
Documentation: General Electric Company compiled the data obtained from the survey and documented Human Engineering Discrepancies for which modifications should be considered. A preliminary prioritization was documented for each discrepancy through the use of the evaluation products, as discussed earlier.
The Summary Report of the Human Factors Design Review Of The Perry Control Room is included as Attachment D.
BWROG SUPPLEMENTAL CONTROL ROOM SURVEY
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k The Supplemental Control Room Survey was performed from Jund 11-15, 1984, which included completion of the BWROG Control Room Survey Checklist Supple-ment and checklist items which could not be completed in the original survey.
Objective: The objective of the Control Room Supplemental Su2vey is to review and assess the adequacy of the arrangementi and identification of important controls and displays, the usefulness of audio and visual alarm systems, plant status information provided, procedures and training with j respect to limitations of existing instrumentation, information recording and recall capability, the control room layout and environment, and other areas of l human factor engineering that potentially impact operator effectiveness. The ultimate objective is to identify potential modifications of the operator-control room interface which will reduce the potential for human error.
Methodology: The Control Room Survey Supplement Checklist is intended to i augment Revision 1 of the BWROG Control Room Survey Program dated 1/1/81. The Supplemental Checklist contains NUREG 0700 checklist items not directly
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addressed in the original BWROG checklist. The desirability of includiig jf {} these items has been verified by the experiences of the BWROG Survey Teams.
v Procedure: The Supplemental Control Room Survey was conducted by the
- Survey Teams using the checklists shown in Attachment C. As before, sections j for panel layout, instrumenta' tion and hardware and annunciators were completed r for_each panel in the control room and division 1 remote shutdown room, including back panels, auxiliary panels and peripheral equipment that con-k I tained controls and displays operated or monitored by the control room opera-0 -
y tor. A list, description and locations of the panels reviewed is contained in 1 ,
%- Attachment K. The checklist for computers was performed for ERIS and the ,
process computer. The checklists: Procedures, Control Room Environment, and
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Maintenance and Surveillance were completed'only once for the entire control room. The procedure for the Supplemental Control Room Survey was the same as ',
the original Control Room Survey. Checklist items not available for review during the first survey but available during the supplemental survey were completed and documented. Checklist items that are still open for review are ,
clearly documented in the HED Report Sheet 360 included in Attachment I.
E i /N s Review Team: The Supplemental Control Room Survey Team was comprised of 1.
j the PNPP Human Factors Unit, two human factors specialists and a General Electric systems engineer. ,,,
Documentation: General Electric Company compiled the data obtained from the Supplemental Survey and documented Human Engineering Observations (HE0's). A
. preliminary prioritization was documented for each HE0 through the use of the evaluation product, as previously discussed. The Summary Report for the Supplemental Control Room Survey dated 9/24/84 can be referenced in Attach-ment A of Attachment E.
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7 NRC IN-PROGRESS AUDIT o The NRC staff and its consultants performed an In-Progress Audit of the Perry Unit 1 Control Room on-site on August 9-13, 1982 and reviewed the June 7, 1982 Interim Detailed Control Room Design Review Report. The In-Progress Audit Report dated 11/12/84 contained four parts:
A. List of items that were not available for review during the NRC Audit, B. Discrepancies identified by CEI in the interim DCRDR Report or by the NRC team during the Audit, C. Discrepancies identified by CEI which the NRC team determined to be either invalid or corrected at the time of the Audit, D. Photographs taken during the Audit.
2.3.2 OPERATOR SURVEY The Operator Survey portion of the DCRDR consisted of two separate surveys:
BWROG Operator Survey and Supplemental Operator Survey.
l BWROG OPERATOR SURVEY I
The BWROG Operator Survey was performed in conjunction with the initial
! Control Room Survey from September 21-25, 1981 in accordance with the BWROG Control Room Survey Program.
Objective: The objective of the Operator Survey is to obtain direct operator input to aid in identifying potential or actual deficiencies in the f
control room layout or design or in operating procedures that result in confusion (mental activities), difficulty (manual activities) or distraction (the environment).
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Methodology are included in Attachment A.
O Procedure: Since experience has demonstrated that more complete answers are obtained when the operators are allowed time to deliberate the questions, a prepared questionnaire included in Attachment B, Section 1 was devised by the BWROG program for the Operator Survey. Thirty operators were asked to complete the questionnaires prior to the arrival of the Survey Team, based upon their simulator experience and knowledge of our control room without consulting other operators. One-third of the operators that participated in the questionnaire were selected to participate in the oral interviews. This sample size was judged to encompass a wide variety of operator opinion based on operator experience, education, ability and physical size. Of the ten operators selected for interviews, five were supervising operators, two
. operation engineers, two operations engineering assistants and one reactor engineer. All ten operators were Perry simulator certified. The General Electric operations engineer trained in interviewing techniques performed all the interviews.
Review Team: The Operator Survey Team was comprised of the PNPP Human Factors O' Unit, a General Electric operations engineer and a human factors specialist.
Documentation: General Electric Company compiled the data obtained from the written questionnaires and the oral interviews and analyzed it to identify specific areas of concern. Attachment D, Appendix B shows the results of the
- Operator Survey.
l l SUPPLEMENTAL OPERATOR SURVEY The Supplemental Operator Survey was performed from June 11-15, 1984 and was conducted to obtain an operating survey update based on training and experi-ence accumulated since the original survey.
Objective: The objective of the Supplemental Operator Survey is to obtain
( direct operator input to aid in identifying potential or actual deficiencies in the control room layout or in operating procedures that result in confusion 1
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(mental activities), difficulty (manual activities) or distraction (the 1
environment).
Methodolomy: The Supplemental Operator Survey methodology is essentially the same as the BWROG methodology for the Operator Survey. The basic difference between the two surveys is the addition of an entire section of questions
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4 directed toward the Perry Plant Emergency Instructions (PEI's) selected from i
j the INPO-NUTAC (83-047) Component Verification and System Validation Guideline i dated 12-83. The Supplemental Operator Survey Questionnaire is included in -
! Attachment.E as Appendix A.
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{ Procedure: The supplemental questionnaire was distributed to operations
} personnel with a wide range of experience extending from the reactor license
! candidates to a previously licensed shift supervisor. Of the 43 questionnaire f respondents, twenty respondents were selected for an oral interview to discuss l and amplify the questionnaire responses. These interviews were conducted on l an individual and private basis with interviews averaging approximately one hour in length. In selecting interviewees, preference was given to those who had received license training. Human factors concerns raised during the l
interviews were photo-documented where possible. The human factor specialist,
! well experienced in interviewing performed all the operator interviews.
Review Team: The supplemental Survey Team was comprised of the PNPP Human Factors Unit and a human factors specialist.
I Documentation: The human factors specialist, J. Seminara coepiled the data obtained from the written questionnaire responses and oral interviews. The j responses of the questionnaire and interview sample were summarized with the total number of comments for each question noted. The report is included in the Detailed Control Room Design Review Findings Perry Nuclear Plant Septem-i bor 24,'1984 in Attachment E of Attachment E.
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!O 2.3.3 TASK ANALYSIS O
V 'Ihe Task Analysis portion of the DCRDR consisted of two separate sections:
Emergency Procedure Guidelines (EPG) Task Analysis, and Plant Emergency Instruction (PEI) and Remote Shutdown Task Analysis.
EPG TASK ANALYSIS The Emergency Procedures Guidelines developed by the BWROG formed the founda-tion upon which the Perry Plant Emergency Instructions were developed. Using these guidelines, a task analysis was performed, in conjunction with the Control Room Survey, which identified instrumentation required to evaluate plant conditions within the framework of the procedural steps. This instru-ment list was then compared to the actual control room inventory to verify that the specified parameters are in fact available to the operator. The results of the task analysis and walkthroughs of the EPG's can be referenced in Section 5 of Attachment D.
PEI AND REMOTE SHUTDOWN TASK ANALYSIS The Task Analysis of the Plant Emergency Inst ructions (PEI's) and Shutdown From Outside The Control Room Integrated Operating Instruction (10I-11) was performed during June 1984. The basic BWROG methodology for performing a task analysis was utilized, with additional considerations incorporated resulting from recent NRC recommendations. The following sections describe each phase separately and are arranged in the order performed. The methodology and procedure sections for each phase are condensed; for further details, refer-ence Attachment F. Perry DCRDR Task Analysis Procedure.
Task Identification 0bjective Identify operator tasks required to implement the Perry Plant Emergency Instructions (PEI's 1-7) from the control room and the Shutdown From Outside The Control Room Integrated Operating Instruction (101-11) for the Div 1 and 2 remote shutdown panels.
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Methodolozy: Tasks were identified from PEI's 1 through 7 Revision 0, 10I-11 DRAFT and sufficient supporting instructions such as the System Opera-tion Instructions (SOI's) and off Normal Instructions (ONI's) which were directly or indirectly referred to by the main procedure. Identicar tasks were only analyzed once.
Procedure: Each discrete task was identified in the Operator Task section and referenced in the Main Procedure section of the CRDR Task Analysis Data Sheet. When the instruction step task from the main procedure was implemented with a supporting SOI or ONI section, then the subordinate discrete task was referenced using both the Main Procedure and the Supplemental Procedure sections.
Review Team: The Review Team was comprised of the PNPP Human Factors Unit with support from instruction writers, engineering and training personnel. A General Electric systems engineer and two human factors specialists reviewed the selection of the task assignments.
Documentation: All main, supplemental and repeat tasks identified are k shown in the Task Identification Sheet included as Attachment G. A total 443 main tasks and 124 repeat tasks were identified. Supporting instruction sections totaled 54 which contained 360 tasks. Tasks are identified in the Task Analysis Data Sheets included as Attachment H.
Information & Control Needs and Requirements Objective: Identification of the information f control needa and requirements necessary to accomplish the operator tasks.
Methodology: A two step analytical process was used to identify the information & control needs and requirements.
The information & control needs were obtained directly from the operator tasks. This was accomplished by itemizing the " task aspects" which were described as information (detect, identify, process), decision (verify, evaluate, choose) and action (monitor, control).
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The information & control requirements were determined from the information ,
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and control needs. Both explicit end implicit requirements were identified.
Procedure: The information & control needs for each operator task aspect
+ identified were noted on the task analysis sheet. These needs were classified as action, decision or information. The information & control requirements were determined from the information & control needs using the above method-f ology.
Review Team: The Review Team was comprised of the PNPP Human Factors Unit
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with support from operations, engineering and training personnel. General ,
4 i Electric systems engineer and human factors specialists reviewed the selection
- A j of the needs and requirements during the walk-talk through analysis.
Documentation: All information & controls needs, type and requirements are documented on the Task Analysis Data Sheets of Attachment H.
3 Information & Control Specific Characteristics
- O Objective: Determination of the necessary characteristics of the information & control requirements.
Methodology: The specific characteristics of the information & control requirements were determined statically, and were only to be identified dynamically if the task aspect specifically designated a transitory require-ment. Specific characteristics of the information and control requirements were identified independently of actual control room configuration. The basis for the specific characteristics was established from either the explicit task, vendor design specification, purchase specification, or anticipated plant / system response; and then verified as acceptable by the Human Factors Multidisciplinary Team. The following specific characteristics were iden-tified: RG 1.97 variable, Parameter, Range, Accuracy, Indication, Control, and Other (e.g. setpoints, explanatory notes.)
Procadure: The appropriate specific characteristica for each information
& control requirement was identified on the task analysis data sheet.
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Review Team: The PNPP Human Factors Unit developed the methodology and identified the specific characteristics with support from I&C engineers. A O General Electric systems engineer and human factors specialists reviewed the specific characteristics during the procedure walk-talk through analysis.
Documentation: Instrument Loop Data Sheets formatted as shown in Attachment F documented the data used to determine the specific characteristics of in-strumentation & control identified in the task analysis. Specific charac-teristics are documented on the Task Analysis Data Sheets in Attachment H.
Instrument Loop Data Sheets are kept in the PNPP human factors file.
gerator Response and Panel Information & Control Objective: Identification of the operator response, and the panel information & control specific characteristics used by the operator to accomplish the tasks at the control panel.
Methodolomy: The operator identified all information & controls necessary to accomplish the specified task. The information & control specific O characteristics were then determined from the control room panels. The following specific characteristics were identified: Panel No., Equip-ment No. , RG 1.97 label coding, Parameter, Ran;;t., Accuracy, Indication, Control and Other (e.g. setpoints, resolutio'is or explanatory notes).
Procedure: The walk-talk through analysis was performed. The operator read the task, then walked through the task aspects at the control panel and explained each in detail. A team member recorded the information & controls used during the walk-talk through in the operator response section of the Task Analysis Data Sheet. Any operator response not specified in the operator task was noted in the contingencies column. Specific characteristics of the panel information & controls were determined and recorded on the Task Analysis Data sheet as specified in the Task Analysis Procedure, Attachment F.
Review Team A control room operator provided the operator responses for O
each task and the PNPP Human Factors Unit, General Electric systems engineer and human factors specialists recorded the operator responses and determined the specific characteristics of the panel information & controls.
Documentation: Operator responses and panel information & control specific characteristics are documented on the Task Analysis Data Sheets. Attachment H.
Background data for such things as accuracles and setpoints are contained on the Instrument Loops Data Sheets in the Perry human factors file.
Verification of Task Performance Capabilities Objective: Verification of the availability and of human engineering suitability of the panel information & control items identified by the operator response.
Methodology: Verification of panel availability was confirmed when the panel information & control item identified in the operator response was sufficient to implement each task as specified by the information & control requirement and specific characteristics.
The verification of human engineering suitability was confirmed by a checklist to review the task performance interfaces: operator to procedure, procedure to plant, and operator to plant.
Procedure The verification of availability and suitability was performed and the decision recorded on the Task Analysis Data Sheet. If the availa-bility and suitability criteria were not satisfied, the reason was recorded.
Review Team: The PNPP Human Factors Unit, General Electric systems engineer, operators and human factors specialists performed the verification of availability and suitability.
Documentation: Availability, suitability and related Human Factors Comments and Notes have been recorded for each task on the Task Analysis Data Sheets included as Attachment H. General Electric evaluated the results of the T ek Analysis and
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Identified Human Engineering Observations in the PNPP DCRDR Findings shown as ,
Attachments B, C and D of Attachment E.
2.3.4 ONGOING HUMAN FACTORS PROGRAM Due to the project awareness and concern for Human Factors, PNPP organisations have submitted Human Engineering Discrepancy Comments to the PNPP Human Factors Unit. These discrepancies are documented in the "1000" series of the HED Report Sheets and Human Engineering Discrepancy Report Sheets in Attach-monts I and J.
. 2.4 ' ASSESSMENT AND SELECTION OF DESIGN IMPROVEMENTS Objectives Assessment of Human Engineering Discrepancies and Observations to identify Human Engineering Deficiencies (NED's). Selection of HED improve-monts. And for those HED's not completely corrected, assessment of the MED's safety and operability significance.
Hethodolomy: During the Assessment Phase each Human Engineering Discrepancy.
or Observation discovered during the review process was reviewed to determine whether the item should be identified as a Human Engineering Deficiency (NED).
Each discrepancy or observation was reviewed for its validity and served as the basis for identifying a HED regardless of the frequency with which the given problem was identified. The following criteria was used to determine whether the observation or discrepancy should not be considered a HED:
o Identical items were analysed only once.
[ o Item did not violate the Human Factors Checklist critaria or was
- inappropriately determined for the Perry control room. .These items I
. were classified as " Disagree" and justification was documented.
L " Disagree" and duplicate items discovered during the NRC In-Progress Audit have been provided in Attachment J.
- o Item was'related to procedure formats. Procedural items were forwarded to the Operations section for resolution.
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A HED improvement selection determined the extent of the modification. The
'" following classifications were identified:
G o Fix -
HED will be corrected, into full compliance with the guideline or benchmark.
o Modify - HED will be improved into partial compliance with the guideline or benchmark, o None - HED will not be corrected since the significance is low and modification for guideline or benchmark compliance is not warranted.
HED's with a "None" or " Modify" implementation classification were assessed for safety and operability significance. The " Modify" HED's were evaluated with regard to the improvement selected. Two categories were formulated on the basis of safety and plant operability consequences. Safety consequence criteria were:
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\' ' o System safety significance - Is HED associated with a significant safety function, or any function necessary to mitigate the significant consequences of an accident?
o Potential consequence - Could HED result in unsafe operation or the violation of a technical specification?
The plant operability criteria was:
o Plant / Operator performance - Does HED increase the potential for causing a significant operating crew error?
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Based on the above criteria each "None" or " Modify" HED received a safety and operability assessment category number:
xs' Category I -
No Safety Consequence
. AND No Increase In Plant Operability Error Potential Category II - Unsatisfactory Safety and/or Operability Assess-ment An unsatisfactory Safety and/or Operability Assessment of Category II for ,,
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"None" or " Modify" HED's causes a reconsideration of improvement design:
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l either an improved modification or a complete fix; the selected improved modification requires reassessment. ,
, The determination of "Fix" and " Modify" HED improvement design, modifications r
j was an integrated effort taking into account the following considerations:
4 o Does the modification fully correct or improve the HED as O
y \s intended?
a o Does the modification introduce new HED's? .
o Does the modification enhance the overall safe operation of the plant?
o Does the modification conform to the PNPP control room stan-dards and conventions?
o Is the modification coordinated with changes from other im-provement programs such as SPDS, R.G. 1.97, Operator Training and PNPP Emergency Procedures?
o Have alternate methods for modification been explored, such as SPDS or Operator Training?
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Procedure: The assessment and selection of design improvements was performed i
.according to the flow chart in Figure 2 using the methodology described.
' pJ Review Team: The Human Factors Multidisciplinary Team consisting of the PNPP
- Human Factors Unit, human factors specialist and a General Electric systems engineer participated in the assessment process. HED design improvements were determined by the PNPP Human Factors Unit with input from operator and train-ing personnel and human factors specialists, i
Documentation: The results of the assessment and selection of design improvement process are documented in the HED Report Sheet sections: Human ,
Factors Review, Implementation, and Safety And Operability Assessment included 4[
~
.' in Attachment I. , -
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PNPP H.F. ASSESSMENT AND IMPLEMENTATION PROCEDURE CT7C] SUPP ON-GOING BWRO] SUPP BWROG HUMA3 FC.CTCIS CWROG TASK OPERATOR OPERATOR CONTROL ROOM CONTROL ROOM ANALY SIS SURVEY PROGRAM SURVEY SURVEY SURVEY y o
< y y t
4 HUMAN ENGINEERING
_ _ _ ASSES M1NT _ _ _ ^
DISCREPANCIES l AND OBSERVATIONS DISAGREE *-
L_____ 9_ __ _ 7 HUMAN NO EN0lNEERING l DUPLICATE -
DEFICIENCY NED'S (NED) l YES l n l PEI ASSION PROCEDURE *- l HE RELATED gg SELECTION OF DE5]NJAPROVgENTS ODIFYINONE HED IMPROVEMENT SELECTION
~ u_--,, , ,
DETERMINE DESIGN l SAFETY. AND OPERABILITY ASSESSMENT l YES -
l
- 1. S AFETY CONSEQUENCES? : C AT 11 l AND q
- 2. CPERABILITY CONSEQUENCES? i l
NO g DOES DESIGN COMPLY WITH l
INTEGRATED REVIEW 7 YE0 YES r MODIFY? _ . _ _ . _
CATI p_ ___
_ VUlF.19 ^10 N l I -___9 ~]
% CORRECT OR IMPROVE l HED7 l l vea y l l l
' g JUSTIFY INCOMPLETE l l I GUIDELINE ! + CAUSE A NEW HED? l l I COMPLIANCE i lYES l L _.._ _ _ "A _ _ :
I
._m___.____________..___; >
t) r - -- - -' ' 9 '"'""# 9 l No IMPROVE HED l BY FUEL LOAD?
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2.5 VERIFICATION Objectivet Verification that the improvements for the Numan Engineering Deficiencies provide the necessary correction and will not introduce new EED's.
l Methodoloay: The improved control room design was evaluated to assure that the selected design improvements both individually and collectively, ade- :
quately correct the deficiencies and do not introduce other HED's. An Inde-pendent Verification Team evaluated the improved control room design with the ;
following methods:
o NED Report Sheet review to verify that the improved design ade-quately complies with the specific human factors guideline or benchmark related to the HED and can be introduced into the control ;
room without creating any unacceptable human engineering discrep- [
- ancies.
l l i o Comprehensive survey of the integrated improved design on the (
O primary control panels using BWROG panel checklists and considering !
possible interactive effects to ensure thats no new HED's are ,
introduced: no significant contribution to increased risk, unre-l l viewed safety questions, or situations in which a temporary re-duction in safety could occur.
l Procedure For the HED Report Sheet review the PNPP Numan Factors Unit lead I engineer presented the detailed description of the MED design improvement and referenced the revised control rn s panel layout drawings where appropriate.
The Independent Verification ' lea. fe.11 owed the procedure described in Attach-ment M to support the verificatte nothodology. The GE consultant recorded i the results of each MED review on the Design Improvement Review Data Sheet as ,
.shown in Attachment M. For the coaprehensive review of the primary control l reen panels P680, P601, P870, F877 and P883; the Human 7setors Unit lead ;
l engineer presented the review items of the BWR00 panel survey checklists. The i Independent Verification Team reviewed the revised panel drawings to napnnd i i i
!O
\ :
to the checklist items and verified that no new HED's were introduced and no
- reductions in safety occurred. !
Review Team: The Independent Verification Team consisted of a human factors specialist, a previously licensed shift supervisor and a senior design ensi-seer from Reliability and Design Assurance. The PNPP Human Factors Unit lead engineer and the General Electric systems engineer documented the results of the verification, presented the DCRDR implementation recommendations and directed the survey of the improved control panels, j Documentation: Control room panel layout drawings were revised to include the ;
HED implementation improvements and were used to support the verification ;
process. These revised panel layout drawings are available upon request. The ,
Verification section of the HED Report Sheets. Attachment I indicates that the i HED was corrected and no new HED's were introduced. The Design Improvement Review Data Sheet for each HED is kept in the PNPP Human Factors File. New HED's discovered during the verification process were documented in the "400" series HED Report Sheets of Attachment I. ,
O 2.6 MANAGEMENT AND STAFFING 2.6.1 MANAGEMENT i
The responsibility for the PNPP DCRDR resides with the Manager of the Nuclear Engineering Department. The DCRDR implementation is the responsibility of the PNPP Human Factors Unit. The Human Factors Unit consists of PNPP engineering and operations personnel to ensure integration of the project objectives and to fulfill the intent of NUREG 0737 Supplement 1.
O 2.6.2 REVIEW TEAM 511tUC1URE AND RESPONSIBILITIES O The Review Team is a multidisciplined team of individuals with the wide range of skills necessary to perform the DCRDR. The team included the following groupes o PNPP Human Factors Unit o PNPP gupport Personnel o Human Factors Specialists ,
o Consultants o Other Utilities Table 2-1 gives an overview of the review team members, associated discipline and involvement in DCRDR activities. Team member resumes and specific tasks performed with approximate levels of effort have been provided in Attach-ment L.
PNPP HUMAN FACTORS UNIT The Human Factors Unit has overall responsibility to implement the PNPP DCADR.
The Human Factors Unit lead engineer provided the administrative and technical direction for the DCRDR. A. Higas served as Human Factors Unit lead engineer from April 1981 thru Harch 1984. His qualifications include 11 years elec-trical/I&C experience at Perry and chairmanship of the BWR00 Control Room Design Review Committee. W. Colvin was promoted to Human Factors Unit lead engineer in May 1984 after having been involved in the DCRDR program from the beginning. His qualifications include 14 years of operations experience and 830 certification. Human Factors Unit members participated in various human factors workshops. Human factors involvement of the Human Factors Unit members outside the Perry control room include: BWR00 committees on control Room Design Review and Display Procedures Integration, BWR00 Control Room Survey Team, INP0 NUTAC's, and IEEE NPEC subcommittee 7 (Numan Factors).
u)
r- . _.- . .. . .. .m Various engineering and operations personnel were assigned full-time to
(] support control room review functions such as technical task performance, administration support and documentation.
PNPP SUPPORT PERSONNEL The Human Factors Unit was supplemented with additional PNPP personnel on a part-time basis for specific tasks as required. Personnel from engineering, operations, technical and training were utilized.
HUMAN FACTORS SPECIALISTS Three human factors specialists worked closely with the review team throughout each phase of the DCRDR. Along with participating in the reviews, they provided human factors expertise to propose and assess alternative design improvements.
CONSULTANTS b
a General Electric systems and operations engineers were utilized for their vendor support and involvement in the BWROG Control Room Survey Program. GE engineers participated in all phases of the DCRDR with the exception of selection of design improvements. They also provided administrative and documentation support.
OTHER (frILITIES Members from two other BWR utilities provided support through the BWROG Control Room Survey Program in performing reviews.
2.7 DATA MANAGEMENT The DCRDR process involved the use of a substantial number of existing docu-monts and preparation of new documents. Human factors documents referenced were from the NRC, EPRI, INPO, IEEE and the military. All documents used or created during the DCRDR process are kept in the Human Factors File to provide i
a design data base for which future control room modifications may be assesn.d I'n and to establish a review data base which can be accessed for NRC audits.
V
. )
2.3 DESIGN IffrEGRATION:
Control room design improvements have been coordinated with design changes resulting from other improvement plans such as SPDS, Operator Training, New
. Instrumentation (R.G. 1.97 and AW S) and Plant Emergency Instructions (PEI's).
SPDS The PNPP Human Factors Unit has been involved in the review of the GE designed SPDS, the Emergency Information Response System (ERIS). Direction was provid-ed for the selection of displayed parameters, display formats and the inte-gration of the terminals into the control room and remote shutdown panel. The Human Factors Unit reviewed the ERIS displays to ensure the displays were consistent and properly integrated with the control room. Design improvements resulting from the DCRDR were also integrated into the ERIS design where applicable.- A human factors specialist (P. Nicholson) viewed the ERIS dis-plays and submitted comments for improvements. Various HED improvements were provided with the ERIS displays.
O R.G. 1.97 R.G. 1.97 improvements were reviewed by the Human Factors Unit prior to implementation in the control room. R.G. 1.97 variables were also identified where applicable in the Specific Characteristics and Panel Information &
Control portion of the task analysis. Types A, I and C instruments designated as Categories 1 and 2 will be identified with a gold diamond on the nameplate so that the operator can easily discern that they are intended for use under accident conditions.
AWS The Numan Factors Unit reviewed the AWS modifications, the Redundant Reactiv-ity Control System with respect to the control room interface. Design consid-erstions such as annunciation, Inop and Bypass, and controls were reviewed and-improved to ensure proper integration into the control room.
O-t
TRAINING The training section was utilized throughout the DCRDR regarding the operator training program and systems technology. During the last year a licensed operator training instructor was designated as the human factors interface t s between training and the Human Factors Unit. The PNPP simulator duplicates the following Unit 1 control panels: P601, P680, P805, P870 and P895. All modifications to the control room panels will be made to the simulator.
Training will provide feedback on any human engineering observation associated with the DCRDR improvements.
3 EMERGENCY INSTRUCTIONS The Plant Emergency Instructions and supporting System Operating Instructions provided input to the DCRDR task analysis and walk-talk through. This task analysis ensured that the PEI information & control requirements will be available and suitable in the control room. Procedural related human engi-neering observations were forwarded to the operation section writing element
- for resolution. DCRDR improvement selections were forwarded to the operations
. Instruction writers to keep the element informed of the design changes before the design changes appear on the plant drawings. The PEI Validation Plan of l
the Procedures Gantration' Package requires that all PEI revisions be reviewed by the Human Factors Unit. ,
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-PNPP DCRDR MULTIDISCIPLINARY TEAM .
CONTROt SUPP supp SELECTION
.op TASK ASSESS- OF DESIGN VERIFI-
SUMMARY
MULTI-DISCIPLINARY DISCIPLINE ROOM ,,ONTROI. SURVEY P ANALYS18 . MENT IMPROVE- CATION REPORT 1EAM SURVEY SURVEY MENTS PNPP H.F. TASK FORCE A. MIGAS l&C/ELEC ENGR S S S S W. COLVIN OPERATIONS ENGR S S S S S S S S S L. LAWRENCE ELECTRICAL ENGR S S S g B. PANFIL SUPERVISING OPERATOR S S S S P. CURRAN ASST. OPERATIONS ENGR S PNPP SUPPORT PERSONNEL D.COBB UNIT SUPERVISOR S M.NEMCEK UNIT SUPERVISOR S SR OPERATIONS ENGR ASST. 4 J.HANLEY H. COON SR DESIGN ENGR S J.KEARNEY LICENSE TRAINING INSTRUCTOR S R. STIFFLER SHIFT SUPERVISOR S CONSULTANTS - GE K.ROSS OPERATION 3 ENGR S S J. HOWARD SYSTEMS ENGR S S S S S g J.HANLON SYSTEMS ENGR S P.STANCAVAGE SYSTEMS A4D RISK ANALYSIS ENGR S I4UMAN FACTORS SPECIALISTS J. SEMIN ARA HUMAN FACTORS S S S S S S S P. NICHOLSON HUMAN FACTORS S S S S S S.ECKERT HUMAN FACTORS S S S OTHER UTILITIES D. THIBODEAUX SYSTEMS ENGR S R. SOJKA SR OPERAT ONS EtlGR S TABLE 2-1
~ . ._ .
I 3.0 CONTROL ROOM DESIGN REVIEW FINDINGS !
O .0ver 1000 human engineering discrepancies and observations were recorded during the various review processes described in Section 2.3. Through a pre-assessment screening process these observations were reduced to 325 valid human engineering deficiencies considered to be within the scope of the control room design review program. This section describes the results of the l assessment screening procedure and provides a synopsis of the major HED findings in each of the nine major guidelines sections cited in NUREG-0700.
i
- 1. Control Room Workspace
- 2. Communications
- 3. Annunciator Warning System l
- 4. Controls
- 5. Visual Displays
- 6. Labels and Location Aids
- 7. Process Computers
- 8. Panel Layout
- 9. Control-Display Integration
{.
- 3.1 ASSESSMENT SCREENING 1
A screening process was employed to reduce the number of discrepancies and observations that the assessment team would be required to analyze. The
! screening methodology is described in Section 2.4 of this report. This pre-I l assessment reduced the number of relevant observations by the following amounts.
L
[ 1. Duplicate observations were identified and eliminated from the list of observations to be analyzed. This eliminated 123 items.
- 2. Observations related to the format or writing of procedures were t
i compiled into a separate list and forwarded to the Perry Operations Section for resolution. This reduced the number of observations to be analyzed by 208 items.
- 3. Many observations were found to be similar, often differing only by the piece of equipment effected by the comment. Wherever possible, similar observations were combined into single observations which referenced multiple pieces of equipment. The observation list was reduced by 256 items through this procedure.
1 These three procedures reduced the number of observations which required analysis from 1072 to 485 items. These remaining observations were further reduced by the assessment team itself by segregating those items found to be
( invalid or already corrected. Items which were found to be invalid or cor-rected by the Human Factors Engineering Branch during the August 1982 NRC in-progress audit, were included in this invalid HED classification. Of the 485 remaining observations, 160 were determined to be invalid and 325 were found to be valid HED's.
HED Report Sheets are included in Attachment I for each of these 325 HED's.
These sheets document the details of each deficiency including the assessment, design improvement selection and verification. The HED numbers conform to a system which identifies the source of the finding.
O.
- 1. HED numbers 1 to 216 were found during.the 1981 BWROG Control Room i
Survey and the 1982 NRC in progress audit.
- 2. HED numbers 300 to 371 were discovered during the 1984 Supplementary Control Room Survey.
- 3. HED numbers 1001 and above were submitted through the Perry On Going-
' Human Factors Program.
3.2 MAJOR ASSESSMENT FINDINGS This section presents a synopsis of the major findings and selected HED improvements in each of the NUREG-0700 guidelines sections. The guideline sections ~concerning Control Room Workspace, Communications, Annunciator Warning System, and Labels and Location Aids are discussed on a control
t
-room-wide basis. Review findings related to the remaining guideline cate-j{} gories are addressed on a panel by panel basis (Controls, Visual Displays, Process Computers, Panel layout and Control-Display Integration).
The HED's were derived from many different sources (survey checklists, task
! analysis and operator interviews) and were classified into one of the nine NUREG-0700 guideline sections. The findings are organized on the basis of the
- guideline section rather than the source of the HED.
3.2.1 CONTROL ROOM WIDE SURVEY FINDINGS The following four sections describe the major human factors deficiencies and design improvements which relate to Control Room Workspace, Communications, Annunciators, and Labels and Location Aids. They are addressed on a control room-wide basis.
I f-CONTROL ROOM WORKSPACE l
26 HED's were found which relate to control room workspace. Of these 26 i
deficiencies, 20 are to be fixed completely. 6 were determined to be of insignificant safety or operability concern and do not warrant modifications.
-The general layout of the control room was found to be quite' adequate. The passageways between the Operators Auxiliary Console P805 and the two benchboard panels P601 and P680 were increased by two inches to provide an acceptable clearance (HED 1). The centrally located support column within the~ control room horseshoe (P601, P680, P870 and P877) that obstructs the view of the panels (HED 11) was assessed as having a low significance.and not corrected.
Lighting level deficiencies were identified for both the control room.and the remote shutdown room (HED 2, 371). Emergency DC lighting levels.in the i primary control room operating area were surveyed below the BWROG and o
- NUREG 0700 lighting guidelines. The improved control room horseshoe DC L
emergency lighting design will provide the minimum recommended 10 footcandles
.of NUREG 0700. The division 1 remote shutdown panel light survey showed about O
5 footcandles on the left side of the panel. The remote shutdown room improved lighting' design will increase lighting levels to the minimum recommended 30 footcandles.
Several environmental deficiencies were noted, primarily related to glare and parallax on recorders and meters (ED 23, 24, 25). The review found that glare (and parallax) did not appear to be a problem when meters and recorders
! 'were read from a normal viewing angle, i.e. in front of the meter. The problem of glare becomes significant as a result of attempting to read the I displays from increasing oblique viewing angles. Glare was also noted as a problem at the remote shutdown panel on the higher displays. This glare problem was reduced when the false floor was installed. When read from a normal viewing position, all displays were found to be readable with no parallax problem and with glare introducing only a slight annoyance.
. Several minor problems were discovered with' work station designs. Throughout-the main control room and remote shutdown panel, numerous. switches, controls and displays were found to be above or below accepted anthropometric standards (ED 17, 18, 19, 20, 21, 300) . In most cases the deviation was insignificant l (less than 4 inches). In those cases where the deviation was more than 4 inches, misoperation or misreading of the effected control or display was
.found to have no significant safety or operability consequence. One modifi-cation was made to address this deficiency at the remote shutdown panel. A false floor was installed to bring an excessively high RCIC controller to within 3 inches of the anthropometric standard. This resulted in the lowering of the transfer switches below the accepted standard. These switches are used to transfer control power from the main control room to the shutdown panel.
It was determined that there is negligible chance that these switches would be l misoperated even at the lower level. The switch handles were also changed to oval handles in order to avoid inadvertent actuation.
l I.aydown space was found to be a problem in the work station design of P680 (ED 22). This problem has been corrected through the use of a procedure holder which attaches to the panel railing. For the benenboard panels a clear plexiglass procedure holder will be provided which rolls en the pancl_ railing and can be easily removed. Procedure laydown space is also available on
! 32 -
j q
4
.the process computer desk (P805) which is located immediately in front of P680.
Deficiencies were found in the available storage space for procedures, draw-ings, personal belongings and protective gear, spare parts and tools (NED 12, !
13, 14, 321, 346, 348, 360). In most cases these deficiencies were due to the construction status of Perry and storage space will be provided.
t Table 3-1 is a summary of all the HED's related to the Control Room Workspace
- guidelines. Implementation for each item is. indicated as "FIX" for complete correction, " MODIFY" for partial correction or "NONE" for no action taken due
- to insignificant safety or operability concerns. For the " MODIFY" and "NONE" classifications, the safety and operability category as described in Section 2.4 is.provided (I or II). A "D" in the "NONE" column indicates that the review team partially disagreed with the finding.
a i COMMUNICATIONS
, 6 HED's were recorded which relate to the communications guideline of NUREG-0700. All 6 are to be fixed completely corrected.
Five of the HED's related to the lack of sufficient voice communications -
1~
capabilities. No dedicated communications link existed between the primary operating area and the shift supervisor's office (HED 15). This problem has been resolved through the use of speed dialing and executive override features on the PBX phone system which provide essentially dedicated phones. The need for more phones throughout the plant was cited (HED 350, 1005, 1014). Five compact multi-function communication system modules have been designed _to
. incorporate two phones systems, the dedicated SOC phone _line,'the plant radio system, the SOC radio channel and the public address system at the three supervisor workstations. Four plant radio and public address system modules will be added-in the horseshoe under the benchboard railings. An additional plant radio and public address system module will be added to panel P969. All communication modules have. phone jacks installed to allow the use of headsets.
The'affected local panels have been provided with additional or relocated phones. The poor compatibility of the breathing equipment with
the control room operator communications requirement will be resolved with special equipment (HED 372).
The problem of unnecessary, distracting page messages being transmitted to the control room was identified (HED 1006). This problem will be corrected by dedicating one channel of the public address system for control room page mes-sages.
- Table 3-2 lists all HED's which relate to the communications guideline.
ANNUNCIATOR WARNING SYSTEM 47 HED's were identified which relate to the annunciator warning system guidelines. 44 are to be completely corrected. 3 of the HED's were determined to be of insignificant safety or operability importance and no modification was justified.
Several deficiencies were found in the visual alarm subsystem. Presently the total number of active annunciator windows is 1158. The annunciator legend readability problems were related to small size lettering, excessive / incorrect
! wordir.;;, inconsistent abbreviations, different font styles, and lack of j- section and matrix labeling (HED 31, 38, 39, 40, 41, 42, 43, 319, 339, 355).
l' In all cases, these problems will be fixed. 60% of the annunciator legends l'
were provided with improved wording. Several problems were found which impaired the operator's ability to quickly identify annunciators. These problems included insufficient color coding of annunciator lights, annunciator l location ~ relative to associated controls, inconsistent grouping or poor arrangement of annunciator matrices (HED 29, 30, 32, 33, 337). In most cases, i
these problems will be fixed completely. Annunciater priority h:s been established by a consistently applied revised color code. Presently 3% of the alarms are coded red-first priority and 12% are coded amber-second priority.
30% of the alarm windows have been repositioned to provide better grouping.
Importan:. trip alarms that were rearranged into function groups are: RPS; DG initiation and trip; ECCS initiation; RCIC initiation, turbine trip and isolation; SPMU initiation; Main Steam Line isolation; Nuclear St.eam Shut.off System isolation; SRV and ADS. This arrangement will improve the man-machine I
s l
[
,, . ~ . , , . . . _ _, . . _ _ _ . - . - - . _ . . . - . . . _ _
interface with those systems requiring prompt attention and immediate operator action.
Significant deficiencies were noted on the operator response subsystem.
Separate acknowledge and reset buttons were not provided, and a silence button was only available on P680 (HED 44, 46). These problems were fixed by replac-ing the acknowledge / reset button with a three function joy stick providing a separate silence function at all annunciator stations. The annunciator controls are physically distinguishable with the new design.
A majority of the deficiencies found related to the general system design and,
{
in particular, the selection of alarm parameters. Several incidences of alarms with multiple inputs were found (HED 26, 27, 37, 322, 1034). A study was performed of the alarms cited. Corrections were made to several alarms.
However, most multiple input alarms were not changed because they were found i to be acceptable to the operator. Instrumentation is available to the opera-tor at the panel to verify most multiple input alarm parameters. Several
_important parameters for which no alarm exists were identified through task analysis of the plant emergency instructions (NED 28, 324, 334, 335, 336,
- 1031). New alarms will be provided for all necessary parameters identified.
Many nuisance alarms were cited by operators (HED 1002,-1003, 1004, 1013, 1033, 1035). All nuisance alarms will be eliminated. Several problems with the logic of certain annunciators were reported by operators familiar with the k -system (HED 1008, 1016, 1018, 1021,-1023). Fixes are planned to correct these logic errors.
l
- Table 3-3 lists all of the HED's related to the annunciator warning system.
1^
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([3) 35 - !
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LABELS AND LOCATION AIDS h Label'and location aid problems accounted for 92 HED's. 89 deficiencies were C
- completely corrected through relatively simple enhancements. 3 HED's were
-~ :
partially corrected with modifications which significantly reduced safety i- risks and operability concerns.
i i
Missing labels and nameplates were found to be a prevalent problem throughout
~
. the control room due to the construction status of Perry 1 (HED 109, 110, 111,.
F 112,.1144 117, 118, 120, 121, 122, 123, 124, 154, 361). In all occurrences j p where labels were missing, they will be provided. A total of about . ,
' 1700 nameplates were ordered for the Unit 1 control room.
- i '
{: . -
t . .
The need for hierarchical labeling was identified in numerous locations
<j - .
.throughout the control room. Frequent redundant labeling was found (HED 125, (' 126,.162). Hierarchical labeling will be employed on the vertical panel-
+
sections in the primary operating area (P601, P680, P870, P877 and-P883) and lon panel P970. The functionally grouped controls and displays on the bench-1 board' apron sections are' effectively presented with mimics. c 4: Several. problems were encountered relative to the content of the label. LIncorrect,' vague or inconsistent wording on labels was found to be confusing' . _ - I to'the operator-(HED 115, 119, 130, 132, 133, 134, 135,-136, 137, 138,'139,
-140, 141, 142, 143, 144, 145, 146, 147, 148, 150, 151, 152, 155, 156, 361, ,
1011, 1012, 1015,'1024). All labels were reviewed and new labels were devel -
,oped and.will be installed to correct errors, clarify wording and use consistent. terminology and abbreviations, as applicable.-
- < .'Several problems.were'found with location aids. Lack of' instrument and control grouping, and subgrouping was a common deficiency that could be
- enhanced through greater use of. demarcation-(HED 159, 160,"161, 162, 163).
Demarcation will be used to correct these problems on.the following panels:
-P601-16B&C, 18B, 19B&Ci 21B&C; P680-4C & 11E1; P800; P845; P865; P870-1B, 4B,
~ ~8C&9B; P881; P882; P883; P904:and P970. . ,
,is v l. 36 - i a, - . T * % e -*b*t 'y W g apew -segety,.ey-g,-aw+dg*---e--gs-ew4g--rdg--M'wg~-=py-g--g--,- sr 9 - 9 i f g- e Y 'zg-ee W*+ar*+ww-+ v- e d *F -ar1+W** e*, w' er
- ww v '
Many minor problems with system mimics were reported. Most deficiencies () involved errors in the m.471c or confusing mimics (NED 165, 166, 167, 168, 170, 172, 173, 175, 176, 307, 308, 311, 328, 359). Other problems included incon-sistent use of color coding in mimics (HED 169, 171, 303) and lack of mimics to show control / feedback or system relationships (HED 158, 301, 302, 304, 305). All deficiencies concerning mimics were reviewed and fixes will be implemented to address the concern. Incorrect mimics were corrected, vague mimics were enhanced to clarify, color code inconsistencies were corrected and mimics were added to clarify control / feedback relationships. Several deficiencies relative to the location of labels on instruments and controllers were found. Some labels were obscured by projecting controls or instruments (HED 127, 129, 331). These problems will be corrected by adding labels in a location where they are not obscured. The one exception is HED-331 which refers to relay contact labels in back panels which are obscured by the installed relay. The operator will no longer be required to see the relay contact labels. Some labels were found on recorder faces which partially obscured the instrument reading (HED 309). This problem was solved by relocat-tO ing the labels. V Table 3-4 contains a complete listing of all HED's related to label and - location aid guidelines. 3.2.2 PANEL / WORK STATION FINDINGS I l Major human engineering deficiency findings in the guideline categories of Controls, Visual Displays, Process Computers, Panel Layout and Control-Display Integration are addressed for each panel or workstation. Emphasis is placed on those panels in the primary operating area and the remote shutdown panel. Backpanels are discussed on a generic basis. GENERIC PANEL / WORK STATION FINDINGS Some deficiencies in the categories of controls, visual displays and panel layout were found on a control room wide basis. Table 3-5 lists the 29 HED's ps recorded of this type. Of these 29 HED's, 25 are to be fixed completely, 3 d 1
. u.. . c'r -- - - - - - - - -
-are to be modified to reduce the significance of the deficiency and 1 will be O ieit c ct4d toits 1 siiricc-Several of the ED's cite the lack of information in the control room which would be required by the operator while executing the plant emergency instruc-tions (ED 9, 73, 199, 325). In all cases this missing information will be
{ provided. In most cases, the information is provided by ERIS. 1 Many of the deficiencies relate to inconsistent data references, process units ! used or scaling technique used on meters and recorders (ED 60, 70, 76, 79, i 80, 81, 314, 364, 1022). In addition, insufficient ranges were often found on i meter and recorder scales (ED 68, 363). Scales on meters and recorders were reviewed and changed, where appropriate, to incorporate consistent process , units and references, and sufficient range indications. All reactor water level indication will be referenced to the top of the active fuel. i Indicator scales were generally not marked or color coded to indicate normal, marginal and abnormal ranges as well as important setpoints (ED 84, 102, 363, l 369). Standard scale color banding will be applied on indicator scales where applicable. I Several ED's addressed the coding of controls. Two ED's noted the inconsis-tent use of colors to code pushbuttons (ED 55, 83). Nineteen pushbuttons were found not to conform to the control room standard and will be replaced. Two other ED's specify that control switch handles have not been shape coded to distinguish switch functions (ED 65, 353). The control switch functions f ( 'will be designated with a standard coding: throttle valve controls will havn silver glove hand operatives; pump and fan controls will have black glove hand operators. Backlit pushbuttons and backlit indicators were not readily l distinguished from one another (ED 92) - The corners of the backlit pushbut-tons will be etched to provide distinction. l The correspondence of chart recorder pens was not a7 ways consistent with the , panel layout -(ED 356). Nine recorder pen channel assignments will be changed to correct this deficiency. t
.O I
t 4 The usage of keylocked control switches was found to be inconsistently applied on six panels throughout the control room (ED 370). The practice of maintain-ing keys-in place on vertical panels can lead to inadvertent bumping and key I bending. The improved design intent for keylocked switches designated for bypass, restraint and test functions is that at power operation all keys j (except the reactor mode switch) should be removed. The keylocked switches for the safety relief valve controls are among the set scheduled for replace-
- ment . .
J Detection of failed indicating lights was the subject of two ED's which are to be partially corrected (ED 85, 86). Most control indicating lights have no test capability so that failed indicating lights can be detected. Since the neon gas lights used as indicating lights, burn out slowly, failing neon lights can be detected as dim lights. The operator will review the control
-panel light status during shift change and surveillances and direct that any j dim or failed light be replaced. Lamp test switches have been provided for the ADS solenoid valves and silver glove hand operators will be provided to identify valves that do not seal in to aid the operator in identifying failed
( lights on mid-positioned throttle valves. 1 ~ The direction of thumbwhell motion in automatic controllers was opposite to the resulting motion of the moving scale (ED 52). This deficiency will be partially corrected by placing beside each thumbwhell a label showing an upended arrow with the word increase beside it, to eliminate any reminiscence ( of another consideration. i Table 3-5 lists all control-room wide ED's related to controls, displays, l
-panel layout and integration of controls and displays.
' PRIMARY OPERATING AREA PANELS i
The panels to be covered in this section include the Reactor Control Console
~ (P680), the ECCS Benchboard (P601), the Diesel Generator Benchboard (P877),
i the Long Response Benchboard (P601) and the Process Computer workstation L L (P805). ERIS shall also be addressed. O i._ , - - - - _ _ _ _ - - . _ . _ _ _ _ . _ _ _ _ . _ . _ , _ _ _ , _ . . _ _ _ _ . , _ _ _ , . . _ , _ _ _ . _ _ _ _ _ _ - - - , _ _ , _ _
I C Unit Control Console (P680) O The unit control console is the operator's primary workstation during normal l operations. From this console, the operator controls and monitors the reactor ! core, the recirculation system, the feedwater system, the reactor water cleanup system, the condenser, the main turbine and the generator, i a-38 HED's were identified at this workstation. 36 of these deficiencies are to ! be completely corrected. 1 HED was modified to enhance safety and reli-ability. 1 of the KED's was found to be a minor problem which posed no threat to safety or operability and no modification was planned. Of the 38 deficiencies noted, 9 related to controls, 23 related to visual displays, 4 related to panel layout problems and 2 concerned control-display integration. The most significant deficiencies with panel 680 resulted from the use of small meters in a high density layout on the left side of the panel (HED 75, 106, 198). This poses two problems for the operator. Due to the high
'O density, a given meter is difficult to locate quickly and due to their small size they are difficult to read. Several fixes were employed to correct this problem. First, the meters were reviewed to determine which parameters would be required to be clearly displayed and readable from the general area. These critical parameters will be prominently displayed in digital windows in the center of the P680 console. The reactor wide range level indication that was
. presented on a small meter will be moved to a Bailey dual pen indicating recorder that will also provide reactor wide range pressure. The four small SRM period meters will be replaced with two dual channel larger meters. In addition, the remaining meters will be made more readable through the usa of color banding on the scales. Hierarchical labeling and demarcation shall be used to enhance the locatability of the meters.
The SOC Load Requested window was identified as not being required for base' load operation (NED 1020). To further provide large easily viewed displays on P680, the process computer output will be changed from two to three digital
-windows that present numerals 2 inches high.
L r i f 'Two HED's involved missing information which the operator would require while
- working at the P680 console (NED 8, 327). These deficiencies were corrected by the addition of the wide range pressure recorder and ERIS display informa-tion.
L. j Two HED's were identified relative to control-display integration discrep-I ancies (HED 306,'1001). The feedback for the redundant rhactivity control l system (RRCS) controls on panel P680 was located on a backpanel not visible from the P680 console (HED 306). This was corrected by the addition of alarms on'the P680 console annunciator matrix and two system status matrices. F The misplacement of an annunciator on the P870 benchboard which had its .
! related controls on P680 was identified (HED 1001) and corrected by moving the
- i
! annunciator to the P680 console above its'as'sociated controls.
- 1 i - .
L Three HED's referred to the inadvertent actuation (HED 51, 56, 99). - Particu- [ larly significant was the lack of separation between manual scram and isola- , 3 - . tion.pushbuttons. This same panel insert contained the nuclear.instrumenta-
- tion bypass switches which could be disturbed when recorder paper was re-
[' placed. The entire panel insert was reconfigured to properly -layout these i^ controls. The' identical pushbuttons for the annunciator acknowledge and I reactor feed pump turbine (RFPT) trip problem was resolved by. replacing the annunciator control with a three function joystick and protecting the RFPT- . trip control with a cover. Several HED's dealt with non-standard and confusing scaled on meters. Non-standard scale divisions (1, 2 or 5 units) were found (HED 81). Scales were missing on some meters (HED 63,.64, 69). Process units were missing on some labels (HED 76). An incorrect scale was found for the wide range water . level scale (NED 101). In all cases these deficiencies were corrected by ( . changing the meter scales and labels. One HED notes-that pointers obscure scale marks on some meters (HED 107). This was .found to have a relatively small effect on the readability of the meters and no correction was made. Table 3-6 lists all HED's which address panel P680 in particular. ECCS Benchboard (P601) The ECCS benchboard contains the controls and instrumentation required to monitor and control the emergency core cooling system including the residual heat removal systems (RHR), the high pressure core spray system (HPCS) and the Division 3 diesel generator, the low pressure core spray system (LPCS), the automatic depressurization system (ADS), the nuclear steam supply shutoff isolation system and the standby liquid control system (SLC). 33 HED's were recorded relative to the P601 panel. 25 deficiencies are being fully corrected, 6 are being modified to improve safety and operability concerns and 2 were determined to be of no safety or operability significance and were not changed. Several HED's were associated with the SRV controls and indication. The absence of direct indication of actual safety / relief valve (SRV) position was detected as a problem from two sources (HED 65, 89). This has been corrected 4 by the installation of SRV tailpipe pressure indication above the SRV controls and on ERIS displays. New nameplates indicate the natural sequence of the SRV layout (HED 202) and indicate the PEI SRV operational sequence to provide the required operator information (HED 203). The lack of reactor pressure indica-tion at the SRV controls (HED 216) was corrected by the dedicated digital wfde range reactor pressure display added on P680 which will be readable from the SRV workstation. Three deficiencies addressed the unavailability of indication. The unavaila-bility of reactor water level indication in the HPCS operating area (HED 197) was partially corrected by providing a division 3 wide range and fuel zone water level indicating recorder five feet away on the RHR A section. The missing RHR LOCA override indication for the ECC pumps A and B (HED 1025) was corrected by providing the proper amber lights. The lack of division 3 diesel generator RPM meter was identified (HED 58), but the assessment team determined that the existing frequency meter was suitable for system operation. Several panel layout deficiencies were corrected by rearranging components. _ The_ isolation matrices were found to provide a poor layout of the isolation
.- .1 - - - _ - , . . _ , . _ . - , - . .
groups and the isolation group valve layouts were not ordered sequentially (ED 365). The isolation matrices have been rearranged to properly identify each of the isolation groups and to organize each group by MPL alphanumeric order. The RHR system layout was noted as appearing somewhat convoluted (ED 165) . This significant deficiency was corrected by moving control switches to " straighten" the flow path mimics for LPCI A, B and C as well as Shutdown Cooling A and B. The inconsistent configuration of four sets of steam line drain valves (ED 204) was restored by exchanging one set of control switches. The drywell and containment pressure and temperature meter layout was rearranged to support the new hierarchical labeling (NED 210) for both division 1 and 2 meters. Three panel layout deficiencies was resolved by location aids. The separation of the two Standby Liquid Control trains on two sections (ED 209) was par-tially corrected by providing red demarcation lines to enable the operator to readily locate and associate the two train groupings. The HPCS section had meters grouped in long unbroken strings of 7 and 10 meters. This deficiency was corrected by applying demarcation lines and hierarchical labels to visually divide the meter strings. The division 3 diesel generator WATIS and VARS circular scales did not correspond with the P877 division 1 and 2 diesel generator vertical scales for the same parameters (ED 57). The application 4 of hierarchical labeling and demarcation partially corrected the inconsistent meter scale layout by enhancing the location and association of these meters. j Several problems were reported with the recorders on panel P601. Two defi- ! ciencies were the RHR Temperature recorder chart was hard to read and frosted (ED 94, 362). This was due to the difficulty in reading the small numerals i l on the paper and the glass cover that was frosted for glare reduction but hard ' to read through. The frosted glass cover will be changed to clear glass to enhance readability. Another deficiency was the requirement that the operator i pull Bailey strip chart recorders out of the panel in order to obtain trend information (ED 104). The assessment team felt that this was an acceptable practice in that this would not cause an operator error. ERIS will have the ! same trend information presented on the displays which will minimize this practice. O { ; l L
Table 3-7 lists all HED's which were observed at panel P601 in particular. Diesel Generator Benchboard (P877) The diesel generator benchboard contains the controls and instrumentation necessary to control and monitor operation of the division 1 and 2 diesel generators. This panel is an extension of the ECCS benchboard (P601). Only 2 HED's were identified on panel P877. 1 is to be fixed completely, and 1 is to be modified to improve operability. Table 3-8 lists the HED's related to pars 1 P877. Long Response Benchboard (P870) d
~
Routine balance of plant operations are monitored and controlled from tha inng response benchboard panel P870. The operator routinely interfaces with this panel during normal plant operation, but has relatively little interface with this panel during emergencies. [) 15 HED's were identified with particular application to panel P870. All but 2 are to be completely fixed. 1 HED was. modified to enhance operator conven-
-lence. 1 HED was found to be of negligible safety or operability concern, and was therefore not fixed.
Three deficiencies were associated with controls. Some controllers were found to have different "close/open", "open/close" indication conventions (HED 354). These inconsistent controllers have been changed to the control ro'om conven-tion. Concern was raised that breaker control switchas nn tha-and of panal i P870 could be inadvertently actuated by brushing against them (HED 357). Different switch handles will be installed which are less susceptible to inadvertent actuation. Also a improper spring return control switch (NED 1032) was properly replaced. One deficiency was found with the panel layout. The condensato inlet valve control arrangement was arranged in reverse numerical order from the top to O 1
bottom of the panel (NED 206). The assessment team noted that this layout was consistent with the remainder of the system controls on the panel supporting the cascading heater drain mimic. Operator error is unlikely and would not effect plant safety. Therefore, no change was warranted. Three control-display integration deficiencies were noted. The reactor feed booster pump controls and indications were located at panel P680, yet a related annunciator was located at panel P870 (HED 1001). The annunciator window was moved to correct this problem. To correct the improper placement of the CRD conductivity recorder (HED 1029), the input was relocated to a pen of a water quality recorder on P680-1D, adjacent to the CRD section on F601-22. The improper placement of the indicating lights for valve N22-F265 below the control switch (HED 1017) was corrected by rearranging the indicating lights and the control switch. Table 3-9 lists all the HED's with particular application to panel P870. ERIS and Process Computer Workstations (P680 & P805) 30 HED's were identified which relate to ERIS and the process computer. 21 deficiencies are to be fully corrected, 4 deficiencies are to be partially corrected and 5 HED's will not be corrected due to their insignificant safety and operability impact. Software security was found to be the subject of two HED's. The absence of procedures or administrative controls for software changes (HED 177) will be remedied by establishing such procedures. Secure, remote storage of software had not been provided for at the time of the review (HED 178). Secure storage of software at a remote location will be provided. Two HED's related to computer operating procedures. The unavailability of computer operating procedures in the control room (HED 320) will be partially corrected by providing computer system description manuals in the control room. The unavailability of procedures to cover failure of the process computer concern (HED 183) has been corrected by the establishment of the 0 4-policy that only the onshift I&C technician shall restore operation of com-puters. O Several deficiencies were noted for the computer keyboards. The temporary labels on the function keys of both ERIS and the process computer (NED 182)
. will be corrected by installing permanent engraved keys. The graphic function keys will be replaced to show only operator keyboard functions (NED 181).
The process computer numeric key pad with one key out of position for a standard calculator style keypad (NED 316) was not corrected since this was assessed not to be significant. Some problems were found with the computer display formats. The abbreviations on the process computer displays and logs are to be made consistent with the Perry control room standard (HED 180). The process computer MPL number, data point addresses have been pr vided with a Point Dictionary Service (HED 186, . 179). The vendor color codes .. sed for the computers will be maintained (NED 188, 198), since within the various computer displays, consistent, 1 logical colors are used, though different from the control panel standard colors. The operator should not be confused by this inconsistency because of the natural recognition that different color coding standards exist. , A few problems were found with the CRT's used for the process computer. Glare on the CRT's at P805 was noted as a problem (NED 317). The P805 CRT glare was found to present an annoyance but not impair usability when examined by a [ human factors specialist. The dispirys were readable; no correction was made. 1 j The remaining two CRT problems noted were improved or corrected by set adjust-ments (HED 185, 187). l Two deficiencies were peculiar to the process computer. The alarm tone of the ( " ding" to attract the operator's attention will be provided with an adjustment { at the keyboard (NED 318). Although a periodic review to assure only useful l information is printed has not been established, a partial correction will resolve changes to the computer output as requested or identified by the plant technical section. l l:
Several ED's were recorded regarding to the computer printers. The lack of high speed printing capability (ED 191, 1007) was corrected by the addition of's high speed (300 lines per minute) line printer. An additional deficiency with the printing feature of the process computer was its inability to priori-tize printout (ED 190). This problem will be addressed through the use of two printers. A dedicated printer will be provided for the process computer alarms. The high speed line printer will be provided for the logs and other output. Indication of the paper supply and a firm annotation surface have been provided (ED 193, 194). The printer functions will now automatically transfer to another device when one is taken off line (ED 195). Table 3-10 lists all of the HED's which relate to the process computer and ERIS. BACKPANELS The remaining panels in the main control room are addressed in this section. 24 ED's were identified which relate to the backpanels of the main control room. 19 are to be completely fixed, 3 are to be modified to enhance safety and operability and 2 were not corrected due to their minor significance. Most all of the deficiencies identified on backpanels were the same obser-vations noted for the control panels in the primary operating area. A large number of the HED's had to do with deficiencies associated with meter and recorder scales. Functional grouping and demarcation has been used extensively on backpanels to improve the association between controls and feedback, and to improve the readability of panels with large strings and matrices of indica-tors and controls. All frosted glass recorder covers will be replaced with clear glass. Table 3-11 presents a listing of those ED's which relate to back panels. O REMOTE SHlTTDOWN PANELS
~ The Perry Nuclear Power Plant, Unit 1, has two redundant shutdown panels which were designed to allow the operator to perform a normal depressurization to cold shutdown conditions in the event that the main control room would become uninhabitable for any reason. The instrumentation and controls at the remote shutdown panels were found to be sufficient to bring the reactor from a condition at which all control rods are in, to cold shutdown.
Both the division 1 and 2 remote shutdown panels were analyzed for human engineering sufficiency. A paper and pencil task analysis was performed on the division 2 panel since it was not yet built at the time of the survey. It was analyzed on an "as designed" basis from panel drawings and instrument and control design data. Of the 14 deficiencies found for the division 1 panel, all 14 are to be completely fixed.
.Two deficiencies were corrected by a task analysis of the remote shutdown panel (ED 6,62).
Most of the HED's related to controls and visual displays. Three cited the
- need for additional information at the panel (NED 5, 89, 343). An ERIS terminal is to be placed in the remote shutdown room to provide this missing information. One deficiency stated the wide range reactor level indication was inadequate and inappropriately referenced (NED 61). Although the specified wide range water level recorder is suitable for the design basis, the ERIS terminal installed in the remote shutdown room will provide the remaining additional ranges. All reactor water level indication will be referenced to the top of the active fuel. The reactor wide range recorder will be rescaled to the design specification as determined during the task analysis (NED 342).
Large transfer switches mounted low on the shutdown panel were cited for their large J-type handles which could be inadvertently actuated (NED 49). This
-problem will be corrected by replacement handles which are of an oval design.
O
Familiar problems with deficient meter and recorder scales were also found at the remote shutdown panel (HED 76, 78, 80, 81). Scale modifications similar to those used for the main control room were used to correct these problems. Inconsistent applications of seal-in versus throttle valve control at the remote shutdewn panels relative to the control room were corrected (HED 341). The RHR, RCIC and SRV controls and displays were found to be poorly grouped (HED 211). The layout of the RHR and RCIC controls was clarified through the use of extensive mimicking. Color padding was used to emphasize the grouping of the SRV controls. The 1 deficiency found for the division 2 remote shutdown panel and related local controls will be corrected with an "as-built" task analysis. A complete list of HED's which relate to the remote shutdown panels in partic-p ular is provided in table 3-12. V Table 3-13 presents a table of all HED's recorded during the Perry Human Factors Program assessment phase prior to the verification phase. Attachment I contains a complete set of HED Report Sheets that can be used in conjunction with table 3-13. 3.3. VERIFICATION FINDINGS Verification that proposed design improvements correct the HED's without introducing new HED's was conducted in accordance with tha mathndn1ngy and procedure outlined in Section 2.5 of this report. The verification team reviewed each design improvement to ensure that the deficiency was corrected and that no new HED was created due to increased safety risk, unreviewed safety questions or temporary reductions in safety. Several minor modifi-cations were made to the details of some proposed design improvements as a : result of the verification review. The modifications ucre suggeste:! by th: l
- verification team in order to further improve a proposed design or to rectify 1
L________________ l
new problems that may have been created by the design improvement as originally proposed. The verification team found that the design improvements or modified O- design improvements did satisfactorily correct the deficiencies without creating new, unacceptable ED's. 9 additional minor ED's were discovered during the verification process. D ese HED's have been documented as HED numbers 400 through 408 in Table 3-14 and in Attachment I to this report. All 9 deficiencies are to be fully corrected. Several of these new ED's were related to panel layout. The verification team noted that the proposed fix for ED-71 resulted in the unnecessary use of four suppression pool level ranges on panel P883. The four scales were found to be redundant (ED 400). One of the four ranges will be removed to correct this problem. Another panel layout problem was found for the P870 moisture separator and reheater displays (ED 408) which will be corrected by rearrange-ment. Several ED's were identified concerning labels and location aids. These O- HED's primarily addressed mimics which could be improved by use of consistent valve symbols (ED 405), addition of mimics for emergency service water tie in to the RNR system (ED 407) and elimination of unnecessary symbols on mimics such as strainers which serve only to clutter the mimic (HED 406). These minor changes were incorporated into the mimics. Section number labels were added to the P601, P680 and P870 benchboards because isolation valve control , locations are referenced by panel section numbers on the P601 isolation , matrices (ED 404). Additional demarcation and hierarchical labeling for the L i P870 section IB electrical distribution displays was developed and found to be j acceptable by the verification team (ED 403). t One deficiency was found with the stator water cooling pump switch (NED 401). ,! Because of the logic of the switch control, an inadvertent generator runback l could occur by slowly moving the control switch through "off"_when changing l the pump line up. The generator runback logic will be changed to avoid this f problem. O
Finally, one deficiency was found regarding the diffarential pressure meters between containment and drywell (HED 402). The information will be more O t ic >>> rr *a arv 11 te ce t i
- airr r *i 1 ar r ere a to the current display which indicates containment to drywell differential pressure to aid the operator during a LOCA transient.
Table 3-14 lists the new "400" series HED's which were found as a result of the verification. O O TABLE 3-1
SUMMARY
OF CONTROL ROOM WORKSPACE ED's HED DESCRIPTION PANEL FIX MODIFY NONE NUREG No. 0700 SECTION 1 OBSTRUCTED PATHWAY 601 F 1 1 OBSTRUCTED PATHWAY 805 F 1 2 EMERGENCY LIGHTING GENERIC F 1 7 MULTI DIMENSION PIBF USABILITY PROCEDURE F 1 10 NO FURNISHINC.' REMOTE S/D F 1 12 STORAGE SPACE - PROCEDURES NONE F 1 13 STORAGE SPACE - PROCED & DRWGS REMOTE S/D F 1 14 STORAGE SPACE - SPARE PARTS NONE F 1 16 PANEL EDGES SHARP 680 F 1 17 RCIC CONTROLLERS OtTT OF REACH REMOTE S/D F 1 18 HIGH CONTROLLER OBSCURES LABEL REMOTE S/D F 1 19 SWITCES TOO HIGH/ LOW REMOTE S/D F 1 21 CONTROLS / DISPLAYS TOO HIGH/ LOW REMOTE S/D F 1 22 LAYIXEN SPACE 680 F 1 25 GLARE ON PANEL / INDICATORS REMOTE S/D F 1 321 SPARE PARTS NOT AVAIL REMOTE S/D F 1 331 RELAY CONTACT ID & ACCESS POOR 618 F 1 _- 331 RELAY CONTACT ID & ACCESS POOR 629 F 1 346 STORAGE RACK LOCATION 805 F 1 348 FUSE PULLER AVAILABILITY MISSING F 1 351 STORAGE AT SO DESK 805 F 1 360 EQUIP NOT YET INSTALLED VARIOUS F 1 1 371 INADEQUATE LIGHTING REMOTE S/D F 1 11 . SUPPORT COLUMN OBSTRUCTS VIEW MAIN AREA I 1 19 SWITCHES TOO HIGH/ LOW 601 I 1 19 SWITCHES TOO HIGH/ LOW 604 I 1 19 SWITCHES TOO HIGH/IDW 632 I 1 19 - SWITCES 700 HIGH/ LOW 670 I 1 19 SWITCHES TOO HIGH/ LOW 671 I 1 19 SWITCHES TOO HIGH/ LOW 672 I 1 19 SWITCHES TOO HIGH/ LOW 800 I 1
- 19 SWITCHES TOO HIGH/ LOW 800 T 1 19 SWITCHES TOO HIGH/ LOW 865 I 1 19 SWITCHES 700 HIGH/ LOW 970 'I 1 i
19 SWITCHES TOO HIGH/ LOW 970 I 1 20 CONTROLS /INDICAT TOO HIGH/IDW BACKPANELS I 1 23 GLARE AND PARALLAX ON PANELS VARIOUS I 1 24 GLARE /PARALIAX ON RECORDERS 600 I 1 24 GLARE / PARALLAX ON RECORDERS 642 I 1
- 24. GLARE / PARALLAX ON RECORDERS 680 I 1
, 24' GLARE / PARALLAX ON RECORDERS 800 I 1 l 24 GLARE / PARALLAX ON RECORDERS 907 I 1 300 ANTHROP 0 METRIC MEASURE 904 I 1 i'.
TABLE 3-2
SUMMARY
OF C0h7ROL ROOM COMMUNICATIONS HED's HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 15 DEDICATED COMMUNICATIONS LINK NONE F 2 350 PHONES & HEADSET JACKS GENERIC F 2 368 RESPIRATOR COMMUNICATION POOR NONE F 2 1005 PAGE PHONE LOCATIONS INSUFF MAIN AREA F 2 1006 PLAST PAGE MESSAGES DISTRACTNG GENERIC F 2
- 1014 COMMUNICATION TO REMOTE PANELS REMOTE PANEL F 2 b
) O i i O 4 a l O l
TABLE 3-3
SUMMARY
OF CONTROL ROOM ANNUNCIATOR HED's HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 28 ADEQUATE ANNUNC - ENTRY CONDIT GENERIC F 3 29 PRIORITY COLOR CODE - ANNUNC GENERIC F 3 31 ANNUNCIATOR PANEL LABELS GENERIC F 3 32 ANNUNCIATOR GROUPING /ARRANGMNT 680 F 3 33 ANNUNC NOT GROUPED BY TYPE GENERIC F 3 34 ANNUN LGND PLATE REPLACE IDENT GENERIC F 3 35 ANNUNC OUT OF SERVICE IDENT GENERIC F 3 36 MISSING OR BLANK ANNUNC TILES VARIOUS F 3 38 SUCCINCT WORDING - ANNUNCIATOR 601 F 3 38 SUCCINCT WORDING - ANNUNCIATOR 680 F 3 38 SUCCINCT WORDING - ANNUNCIATOR 800 F 3 38 SUCCINCT WORDING - ANNUNCIATOR 870 F 3 40 ALPHA-NUMERIC CODE LABEL-ANNUN GENERIC F 3 41 SMALL ANNUNC' LETTERING 680 F 3 42 3 DIFFEREhT FONTS USED-ANNUNC 680 F 3 43 TEMPORARY LEGENDS - ANNUNCIAT 870 F 3 44 SEPARATE ANNUN ACKhVDG/ RESET GENERIC F 3 45 ONLY 1 ANNUNC SILENT BWTON 680 F 3 46 DIFFERENT STYLE ANNUNC B'JITONS 680 F 3 b, V
) 319 SCRAM TRIP ANNUNC LABEL WRONG 680 F 3 322 MULTIPLE ANNUNC FOR MSIV RAD 680 F 3 324 NO SINGLE SCRAM ANNUNCIATOR GENERIC F 3 329 NO TURBINE TRIP INDICATION MISSING F 3 332 NO SINGLE BOP ISOL INDICATION MISSING F 3 334 NO SIMPLE INDIC OF MSIV LOGIC MISSING F 3 335 NO RCIC ALTTO START LOGIC INDIC MISSING F 3 336 NO ADS TIMER EARLY WARNING MISSING F 3 337 SUPP POOL HI TEMP ANNUNC MATRX 601 F 3 339 RPV LVL 1 ANNUNC LEGEND WRONG 601 F 3 355 ANNUNCIATORS TOO SMALL 680 F 3 366 ANN 0YING ANNUNC AUDITORY ALARM GENERIC F 3 1002 SLC 00S ALARMS WHEN WORKING 601 F 3 1003 MULTI INPUT-RADWASTE TRBL ALRM 680 F 3 1004 CHILLER ALARMS NUISANCE 800 F 3 l
l 1004 CHILLER ALARMS NUISANCE 904 F 3 ! 1008 ' WATER TREATMNT BLDG ALRM MASK REMOTE PANEL F 3 1013 RPV SIPHON NUISANCE ALARM 601 F 3 t 1016 DC BUS UNDERVOLTAGE ALRM LOGIC 877 F 3
'1018 MAN ISOL SVTCH ARMED ALARMS 601 F 3 1023 ANNUNC NOMENCLTR-RCIC/RHR ISOL 601 F 3 1031 INSUFF EVACUATION ALARMS MISSING F 3 l 1033 RFPT TRIP ANNUNC-NUISANCE ALRM 680 F 3 1034 ECCS PUMP TRIP ALARM FRIORITY 601 F 3 1035 SUPP POOL M/U NUISANCE ALARM 601 F 3 30 ANNUNCIATORS ABOVE CONTROLS 680 F D 3 i
i1 i TABLE 3-3 (Cont'd)
- (O /-
SUMMARY
OF CONTROL ROOM ANNUNCIATOR HED's HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 30 ANNUNCIATORS ABOVE CONTROLS 870 F D 3 32 ANNUNCIATOR GROUPING /ARRANGMNT 601 F D 3 32 ANNUNCIATOR GROUPING /ARRANGMhT 800 F D 3 37 SPECIFY ALARM IhTENT VARIOUS F D 3 39 INCONSIST ANNUNC ABBREVIATIONS 680 F D 3 39 INCONSIST ANNUNC ABBREVIATIONS 870 F D 3
- 1021 H2 ANALYZER ALARMS LOGIC 870 F D 3
~ '
26 MULTIPLE INPUTS (ANNUN) 601 I 3 26 MULTIPLE INPUTS (ANNUN) 680 I 3 26 MULTIPLE INPUTS (ANNUN) 845 I 3 26 MULTIPLE INPUTS (ANNUN) 870 I 3 26 MULTIPLE INPUTS (ANNUN) 877 I 3 27 MULTIPLE INPUT LPCS PRES ANNUN 601 I 3
'1019 SATELLITE ANNUNC ALARM LOGIC GENERIC I 3
'% ,a (G ,
E h i s 4 W \
.- 3 55 -
TABLE 3-4 (D
\_/
SUMMARY
OF C0hTROL ROOM LABELS AND LOCATION AIDS HED's HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 3 ALTERNATE PROCESS UNITS 870 F 6 109 . UNLABELED INDICATING LIGHTS 669 F 6 109 UNLABELED INDICATING LIGHTS 672 F 6 110 FUNCTION LABELS MISSING VARIOUS F 6 111 SYSTEM LABELS ON PANELS VARIOUS F 6 112 PANEL NUMBER AND FUNCTION ids GENERIC F 6 113 DIFFICULT TO CORRELATE RX LVL 601 F 6 114 PEN COLOR ID NOT LABELED VARIOUS F 6 115 ESCUTCHEONS INCORRECT REMOTE S/D F 6 117 NO LABELS ON LVL RECRDR/INSTRU 680 F 6 118 LABELS MISSING ON 3 CONTROLS 805 F 6 119 LABEL NOT DESCRIP.0F FUNCTION 805 F 6 120 MISSING PUSH-BUTTON LABEL 680 F 6 121 UNLABELED SELECTOR SWITCHES 883 F 6 122 MISSING LABELS - ISOL VLV CONT 881 F 6 122 MISSING LABELS - ISOL VLV CONT 882 F 6 123 ANNUNCIATOR CONTROL NO LABEL 604 F 6 124 TURB TRIP / RESET NO LABELS 680 F 6 125 HIERARCHICAL LABELING NEEDED GENERIC F 6 -[ 126 REPETITIVE LABELING GENERIC F 6 129 LABELS OBSCURED BY CONTR/ INSTR 680 F 6 130 INCONSISTENT LABELS 601 F 6 130 INCONSISTENT LABELS 631 F 6 131 VALVE CONTROLS ONLY BY NUMBER 865 F 6 132 RCIRC MISLABELED AS "RCIC" 632 F 6 133 NAMEPLATE LABELS INCORRECT"1P" 870 F 6 134 CENTER POSIT MARKING CONFUSING 632- F 6 135 LABEL UNCLEAR 881 F 6 135 LABEL UNCLEAR 882 F 6 136 LABEL INCORRECT B21-F015 601 F 6 137 INCORRECT LABEL G33-R602 680 F 6 138 COND VAC TRIP RESET LABL VAGUE 680 F 6 139 NAMEPLATE LABELS REVERSED (N22) 870 F 6 140 N25-F120A(B),F125A(B) LABL WRG 870 F 6 141 -ID NUMBERS REVERSED ON LABELS 870 F 6 142 RFPT OVERRIDE SWITCH MISLABEL 870 F 6 143 RFPT LUBE OIL TEST LABEL VAGUE 870 F 6 144 1N22-F270 INCORRECT LABEL 870 F 6 145 1N33-C001A LABEL-WORD MISSING 870 F - 6 146 IN62-F010 LABEL TOO VAGUE 870 F 6 147 1N22-F260A(B) MISLABELED 870 F 6 148 MISLEADING LABEL-STATOR PUMP 870- F D 6 149 ESCUTCHEONS WITH NO CONTROL 870 F 6 150 LABEL SYNTAX INCONSISTENT GENERIC F 6 TABLE 3-4 (Cont'd)
SUMMARY
OF CONTROL ROOM LABELS AND LOCATION AIDS HED's HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 151 INCONSISTENT TERMIN0 LOGY 601 F 6 151 INCONSISTENT TERMINOLOGY REMOTE S/D F 6 153 LABELS WORDY GENERIC F 6 154 MISSING NAMEPLATES 669 F 6 154 MISSING NAMEPLATES 800 F 6 155 CENTER SWITCH POS LABL INCONSI GENERIC F 6 156 "AUT0" SHOULD BE " NORMAL" 680 F 6 156 "AUT0" SHOULD BE " NORMAL" 870 F 6 156 " NORMAL" SHOULD BE "AUT0" 870 F 6 158 SYSTEM LOCATION AIDS LACKING REMOTE S/D F 6 159 LACK OF DEMARCATION GENERIC F 6 160 SYSTEM GROUPING AIDS NEEDED MAIN AREA F 6 161 GROUPS VS SUBGROUPS 845 F 6 161 GROUPS VS SUBGROUPS 865 F 6 161 GROUPS VS SUBGROUPS 881 F 6 161 GROUPS VS SUBGROUPS 882 F 6 161 GROUPS VS SUBGROUPS 883 F 6 161 GROUPS VS SUBGROUPS REMOTE S/D F 6 162 HIGH INSTR DENSITY / VISUAL CUES MAIN AREA F 6 163 HPCS DEMARCATION FROM DG 601 F 6 (VQ 164 TURB TRIP / RESET COLOR CODE? 680 F 6 165 MI!!IC CONVOLUTED 601 F 6 165 MIMIC CONVOLUTED 800 F 6 165 MIMIC CONVOLUTED 904 F 6 165 MIMIC SHOWS SRVs IN SERIES 601 F 6 167' MIMIC-ACCENTUATE MAJ ECCS FLOW 601 F 6 163 TEMP STRT/STOP POINTS ON MIMIC 601 F 6 16!) COLOR CODE INCONSISTENT GENERIC F 6 170 MIMIC-MULTI USE OF WHITE DASH 601 F 6-171 BLUE MIMIC SHOULD BE GRAY 800 F 6 172 NEED MORE FLOW ARROWS 904 F 6 173 MIMIC NEEDS FLOW DIRECTION 870 F 6 174 TEMPORARY MIMICS W/ TAPE 601 F 6 175 POOR MIMIC FOR SUPP POOL 601 F 6 176 MIMIC START /END POINTS VAGUE 800 F 6 214 SWITCH / CONTROL RELATION UNCLEAR REMOTE S/D F 6 302 INDICATIONS / MIMICS INTEGRATION REMOTE S/D F 6 303 ECC WATER MIMIC COLOR WRONG 601 F 6 305 MIMIC /DEMARCAT CHANGES NEEDED 800 F 6 307 MIMIC ARROWS NOT STANDARD 808 F 6 308 SYMBOLS VS ARROWS ON MIMIC 904 F 6 309 LABELS OBSCURE INFO 600 F 6 309 LABELS OBSCURE INFO 614 F 6 O
TABLE 3-4 (Cont'd)
SUMMARY
OF C0!UROL ROOM LABELS AND LOCATION AIDS HED's HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 309 LABELS OBSCURE INFO 811 F 6 309 LABELS OBSCURE INFO 823 F 6 309 LABELS OBSCURE INFO 842 F 6 309 LABELS OBSCURE INFO 865 F 6 309 LABELS OBSCURE INFO 883 F 6 309 LABELS OBSCURE INFO 907 F 6 310 EXTRANEOUS INFORMATION 601 F 6 311 MIMIC LACKS HEAT EXCHANGER 800 F 6 312 DUAL SCALE METER 868 F 6 312 DUAL SCALE METER 869 F 6 328 . GENERATOR BREAKER MIMIC WRONG 680 F 6 330 FUSE IDENTIFICATION POOR 691 F 6 330 FUSE IDENTIFICATION POOR 692 F 6 330 FUSE IDENTIFICATION POOR 693 F 6 330 FUSE IDENTIFICATION POOR 694 F 6 331 RELAY CONTACT ID & ACCESS POOR 618 F 6 331 RELAY CONTACT ID & ACCESS POOR 629 F 6 347 COLOR CODE PEI BINDERS MAIN AREA F 6 358 UNCLEAR MIMICS 870 F 6
.O-~
359 MIMIC UNCLEAR 601 F 6 359 MIMIC UNCLEAR 655 F 6 1011 VLV SWTCH NAMEPLATES NORM / AUTO VARIOUS F 6 1012 VLV SWTCH NAMEPLATES OPEN/ AUTO VARIOUS F 6 1015 NAMEPLATE DISCREPANCY 881 F 6 1024 COMB GAS DW PURGE VLV NAMEPLTS 800 F 6 127 PROJECTNG SWITCH OBSCURE LABEL VARIOUS F D 6 152 ABBREVIATIONS INCONSISTENT GENERIC F D 6 161 GROUPS VS SUBGROUPS 680 F D 6 301 NO FEEDBACK FOR ISOL SYSTEM 655 F D 6 304 CONTROL FEEDBACK NOT AVAIL 654 F D 6 361 NAMEPLATE / LABEL LIST VARIOUS F I- 6 116 ISOL MATRIX LABELED BY # ONLY 601 I 6 128 CONTROLLER LABEL PLACEMENT VARIOUS T 6 344 SML INSTR-COMPLICATED CONTROLS 680 I 6 i i [ k V I
TABLE 3-4 (Cont'd)
SUMMARY
OF CONTROL ROOM LABELS AND LOCATION AIDS HED's HED DESCRIPTION PANEL FIX HODIFY NONE NUREG
;- NO. 0700 SECTION 310 EXTRANEOUS INFORMATION 680 I 6 310 EXTRANEOUS INFORMATION 800 I 6
-310- EXTRANEOUS INFORMATION 807 I 6 310 EXTRANEOUS INFORMATION 808 I 6 310 EXTRANEOUS INFORMATION 809 I 6 310 EXTRANEOUS INFORMATION 811 I 6 310 EXTRANEOUS INFORMATION 823 I 6 310 EXTRANEOUS INFORMATION 842 I 6 310 EXTRANEOUS INFORMATION 845 I 6 310 ' EXTRANEOUS INFORMATION 846 I 6 310 EXTRANEOUS INFORMATION 865 I 6 310 EXTRANEOUS INFORMATION 868 I -6 310 EXTRANEOUS INFORMATION 869 I 6-310 EXTRANEOUS INFORMATION 883 I 6 310 EXTRANEOUS INFORMATION 902 I 6 310 EXTRANEOUS INFORMATION 904 I 6 310 EXTRANEOUS INFORMATION 906 I 6 310 EXTRANEOUS INFORMATION 907 I 6 310 EXTRANEOUS INFORMATION 969 I 6 i-I o
l i l- l
T 4 TABLE 3-5
SUMMARY
OF GENERIC CONTROL, DISPLAY AND PANEL LAYOUT HED's HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 9 CONT WATER LEVEL INDIC UNAVAIL MISSING F 5 54 SHAPE-CODED SWITCH HANDLES GENERIC F 4 55 PUSHBUITON COLOR STANDARD PRIMARY F 4 60 VARIED SUPP POOL W/L REFERENCE GENERIC F 5 70 INCONS PRESS UNITS INSTR / TRIPS GENERIC F 5 73 NO " AVERAGE" DW OR SP TEMP MISSING F 5 76 NO PROCESS UNITS ON LABELS VARIOUS F 5 79 RX W/L INSTR REFERENCES DIFFER GENERIC F 5 80 INTERMEDIATE MARKINGS ON SCALE VARIOUS F 5 81 SCALE DIVISIONS OF 1, 2 OR 5 VARIOUS F 5 83 INCONS PUSHBUITON COLOR CODE GENERIC F 4 84 COLOR CODE FOR NORM /ABN RANGE GENERIC F 5 91 REPLACEMENT OF TILES ERROR GENERIC F 5 92 BACKLIT PB & INDIC NOT DISTING PRIMARY F 5 98 MARK TO SHOW SIZE / TYPE PAPER GENERIC F 5 100 RECORDER RANGE BANDING NORM /AB GENERIC F 5 102 ACTION LEVEL MARKING ON SCALES GENERIC F 5 105 NO ALARM POINTS ON RECORDERS GENERIC F 5
~
199 DW TEMP N/A NEAR REFERENCE LEG MISSING F 8 325 NO AVG SUPP POOL TEMP INDICAT MISSING F 5 353 STROKE VALVE IDENTIFICATION GENERIC F 4 356 CHART RECORDER PEN LAYOUT VARIOUS F 9 363 RANGE LIST, INDICATOR SCALES VARIOUS F 5 364 SCALES NON-STANDARD LIST VARIOUS F 5 369 SCALES HARD TO READ VARIOUS F 5 370 KEY OPERATEP SWITCHES INAPPROP VARIOUS F 4 1022 INCONSISTENT VAC/ PRES UNITS GENERIC F 5 , 68 INADEQ SUP P00L LVL RANGE / ACCU GENERIC F D 5 96 DUAL SPEED RECORDERS IDENT. GENERIC F D 5 314 PROCESS UNIT LIST VARIOUS F D 5 52 THUMBWHEEL MOTION OPPOSITE GENERIC I 4 85 DETECTING FAILED IND. LIGHTS GENERIC I 5 86 NO LAMP TEST CAPABILITY GENERIC I 5 97 POINT SELECT ON MULTIPOINT REC GENERIC I 5 O v
- e ,
_- c _ _ __ .
.n ,_ . - .1 _
1 + 4 TABLE 3-6
~ O
SUMMARY
'0F UNIT CONTROL CONSOLE (P680) HED's HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 8- NO W/R RX PRESS RECORDER 680 F 5 48 REACTOR MODE: SWITCH MISSING 680 F 4 50 TURB TRIP PB INADVERTENT ACTUA 680 F 4
~
51 MAN SCRAM /ISOLAT BUTTONS SAME 680 F 4 55 PUSH BUITON COLOR STANDARD 680 F 4 t 56 ANNUN ACK/RFPT TRIP SIMILARITY- 680 F 4 63 PSIA METERS NO LABELS / SCALES 680 F 5 64 BLANK METERS INSTALLED 680 F 5 69 NO SCALE ON RX PRESS METER 680 F 5 72 RFP/MFP FLOW SCALES DIFFERENT 680 F 5 75 SMALL INDICATORS HARD TO READ 680 F 5 76 NO PROCESS UNITS ON LABELS 680 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 680 F 5 90 GREEN LIGHTS DIM 680 F 5 92 BACKLIT PB & INDIC NOT DISTING 680 F 5 93 NO PAPER IN RECORDERS 680 F 5 99 RECORDER INTERFERES W/ CONTROLS 680 F 5 101. INCORRECT WIDE RANGE W/L SCALE 680 F 5 201 INNAPPROP LRG/ CIRC RFPT METERS 680 F 5 i 306 RRCS FEEDBACK ON DIFFER PANEL 680/C22-P001 F 9 l 323 APRM/IRM RECORDER PAPER SCALE 680 F 5 j 327' NO SINGLE INDICATOR FOR 5% PWR 680 F 5 333 RPV PRESS. RECORDER READABILITY 680 F 5 345 NO MECHANICAL STOP-RFP B CONTR 680 F -4 349 RX PRES METER GROUPNG CONFUSES 680 F 8 370 KEY OPERATED SWITCHES INAPPROP 680 F 4 1001 -PSBP CONTROLS NOT NEAR ANNUNC 680 F 9 (. 1020 SOC DIGITAL' WINDOW USEFULNESS :680 F 5 I 1026 FCV CAVITATE INDIC LITE LOGIC 680 .- F 5 m 1027 XFMER DISCONNECT INADV ACTUATE' 680 F 4 l 1028 NON-STAND GREEN PERMISIV LIGHT 680 F 5 1030 NON-STAND AMBER PERMISIV LIGHT- 680 F 5 1036 'TURB FIRST STAGE SCALE UNITS 680 F 5 j.- 1037' RX LVL CONTROLLER ARRANGEMENT 680 F S L 106 INSTRUMENT HIGH DENSITY 680 F D 8 198 HIGH DENS /SML INSTR-RX W/L 680 F D 8 I. 344 SML INSTR-COMPLICATED CONTROLS 680 I 4
.344 SML INSTR-COMPLICATED CONTROLS 680 'I 6 107 . POINTERS OBSCURE SCALE MARKS 680 I 5 L.
TABLE 3-7
SUMMARY
OF ECCS BENCHBOARD (P601) HED's f n HED DESCRIPTION PANEL FIX MODIFY NONE NUREG~ NO. 0700 SECTION 47 DG-3 VOLT SWITCH MISSING 601 F 4 53 NON-CONVENT MSIV SWITCH MOTION 601 F 4 55 PUSH BUITON COLOR STANDARD 601 F 4 59- REACTOR WL' INDICATOR BELOW TAF 601 F 5 65 NO DIRECT SRV POSITION INDICAT 601 F 5 80 INTERMEDIATE MARKINGS ON SCALE 601 F 5 81 SCALE DIVISIONS OF 1,2, OR 5 601 F 5 E9 NO SRV ACT>AL POSITION INDIC 601 F 5 - 93 NO PAPER IN RECORDERS 601 F 5 L 94~ RECORDER CHARTS HARD TO READ 601 F 5 165- MIMIC CONVOLUTED 601 F 8 200 ILLOGIC ISOL STAT TILE GROUPNG 601 F 8 202 SRV CONTROL ARRANGEMENT 601 F 8 204 INCONSIST VALVE CONTROL LAYOUT 601 F 8 r 210 DW PRESS & TEMP NOT ADJACEhT 601 F 8 212 LONG STRINGS OF-METERS 601 F 8 , _216 RX PRES /SRV CONT NOT ADJACENT 601/680 F 9 326 NON-STAND USE OF AMBER LIGHT 601 F 5 338 REG GUIDE 1.97 INSTR RANGE 601 F 5 362 FROSTED GLASS 601 F 5 365 ISOLATION MATRIX 601 F 5 370 KEY. OPERATED SWITCHES INAPPROP 601 F 4 1010 E51-F063 SWITCH LACKS AUTO POSI-601 F 4 1025' ECC PUMP OVERIDE-NO AMBER LITE 601 F .5
-71 INADEQ SUP POOL RANGE /ZERO POS 601 .F D 5 57 INCONSISTENT DG WATTS /VARS METERS 601 I 5
.104 TIME HISTORY CAN'T BE SEEN 601~ I 5
- 197 RPV LVL NOT NEAR HPCS C0hTROLS 601 I 9
.203 INCONSISTEhT SRV LAYOUT 601 I D 8 209 SLC DIVIDED B1VN PANELS 601 I 8 208 INCONSIST LAYOUT FOR DIV1/DIV2 601 I D 8 4
58 DG3 RPM NOT-AVAIL 601 I 5 207 INCONSIST RCIC 00S ARRANGEMENT 601 I 8 t
. - ,, _ . . _ . . . _ . . . _ . . . . _ , _ _ . _ _ . - . . _ . . - _ ___.-_c_,___._..,_..._.___.
j TABLE 3-8
SUMMARY
OF DIESEL GENERATOR BENCHBOARD (P877) HED's 4' HED DESCRIPTION PANEL FIX MODIFY NONE NUREG 0700 NO. ' SECTION 87 DG-2 OOS INDIC TILE NOT ETCHED 877 F 5
^
1 57 INCONSIST DG WATTS /VARS METERS 877 I 5 + 5 t l 1 . O l 1 O i l
TABLE 3-9 O
'd
SUMMARY
OF LONG RESPONSE BENCHBOARD (P870) HED's HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 55 PUSH BLTITON COLOR STANDARD 870 F 4 66 ALTERNATE PROCESS UNITS 870 F 5 67 CST LVL UNITS INCONS W/PROCED 870 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 870 F 5 82 PRESSURE METER UNITS DIFFER 870 F 5 92 BACKLIT PB & INDIC NOT DISTING 870 F 5 93 NO PAPER IN RECORDERS 870 F 5 354 "CLOSE/0 PEN" VS "0 PEN /CLOSE" 870 F 4 357 BRKR CONTROL SWITCH INADV ACTU 870 F 4 1001 RFBP CONTROLS NOT NEAR ANNUNC 870 F 9 1017 INDICATING LIGHTS BELOW CONTRL 870 F 9 1029 CRD CONDUCTVTY RECRDR LOCATIrN 870 F 9 1032 N11-S23 SPRING RETURN /S m g 870 F D 4 104. TIME HISTORY CAN'T Bd SEEN 870 I 5 206 CONDENSATE INLET VLV ARRANGMNT 870 I 8 t" k)/ k L) TABLE 3-10
SUMMARY
OF PROCESS COMPtTTER AND ERIS HED's 1 NED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 177 'SOF1VARE CHANGE ADMIN ADMIN F 7 178 SECURE STORAGE OF SOF1 WARE ADMIN F 7 179 ALARM ACKNOWLEDGE TOO GENERAL COMPUTERS F 7 180 PLANT / COMP ABBREV INCONSISTENT COMPUTERS F 7 181: UNNECESSARY GRAPHIC FUNCTIONS COMPUTERS F 7 182 ENGRAVED LABELS / TEMP LABELS COMPUTERS F 7 183 PROCESS COMP FAILURE PROCEDURE ADMIN F 7 184 NO CROSS INDEX FOR DATA POINTS COMPlTTERS F 7 186 CONFUSING ENTRY FORMATS COMPUTERS F 7 187 CRT PAGE SPACING (TOP & BOTTOM) COMPlTIERS F 7 188 CRT COLOR USE NON-STANDARD COMPUTERS F 7 189 CRT COLOR CODING INCONSISTENT COMPITTERS F 7 190 PRINT 0tTT NOT PRIORITIZED COMPUTER F 7 191 NO HIGH SPEED PRINTING . COMPUTERS F 7 193 PRIhTER PAPER SUPPLY COMPtTIERS F 7 194 NO PRINT 0tTr ANNOTATION SURFACE COMPtTTERS F 7 l 195 PRINTER OFF FOR PAPER RELOAD COMPtTTERS F 7 196 PAPER / RIBBON CHNGE INSTRUCTION COMPUTERS F 7
'318 . INSUFFICIENT MESSAGE HIGHLIGHT PROCESS COMP F 7 367 C91 TERMINAL KEYBOARD STICKS PROCESS COMP F 7 1007 SLOW SPEED TYPER PROCESS COMP F 7 4 SOFIVARE OUTPUT CHANGE COMPUTERS I 7 185 HARD TO DISTINGUISH C,0,0,G,D COMPUTERS I 7
-320 COMP PROCEDURES NOT IN PLACE ADMIN I 7 320- ERIS PROCEDURES NOT IN PLACE REMOTE S/D I 7 192 REMOTE PRIhTING NOT CONFIRMED COMPUTERS I 7 315 CRT - HARD COPY-SOME, NOT ALL PROCESS COMP I 7
, 316 KEYBOARD NOT STANDARD STYLE . PROCESS COMP I 7 317 CRT GLARE FROM WHITE TABLE TOP PROCESS COMP I 7 352' PC KEYBOARD VS DIRT 805 I 7 O
,_ TABLE 3-11
SUMMARY
OF BACKPANEL HED's HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 74 LOG SCALE INTERMEDIATE MARKS 907 F 5 76 NO PROCESS UNITS ON LABELS 619 F 5 76 NO PROCESS UNITS ON LABELS 811 F 5 76 NO PROCESS UNITS ON LABELS 845 F 5 77 SCALES NOT MARKED OR UNCLEAR 823 F 5 77 SCALES NOT MARKED OR UNCLEAR 842 F 5 80 INTERMEDIATE MARKINGS ON SCALE 622 F 5 80 INTERMEDIATE MARKINGS ON SCALE 623 F 5 80 INTERMEDIATE MARKINGS ON SCALE 632 F 5 80 INTERMEDIATE MARKINGS ON SCALE 642 F 5 80 INTERMEDIATE MARKINGS ON SCALE 669 F 5 80 INTERMEDIATE !!ARKINGS ON SCALE 670 F 5 80 INTERMEDIATE MARRINGS ON SCALE 671 F 5 80 INTERMEDIATE MARKII9S ON SCALE 672 F 5 80 INTERMEDIATE MARKING 6 ON SCALE 811 F 5 80 INTERMEDIATE MARKINGS Oli SCALE 821 F 5 80 INTERMEDIATE MARKINGS ON SCALE 823 F 5 80 INTERMEDIATE MARKINGS ON SCALE 842 F 5 rs 80 INTERMEDIATE MARKINGS ON SCALE 845 F 5 ( 80 INTERMEDIATE MARKINGS ON SCALE 970 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 622 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 669 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 672 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 800 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 821 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 823 F 5 81 SCALE DIVISIONS OF 1,2 OR S 842 F 5 81 SCALE DIVISIONS OF 1,2 OR S 904 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 970 F 5 90 GREEN LIGHTS DIM 800 F 5 90 GREEN LIGHTS DIM 881 F 5 90 GREEN LIGHTS DIM 882 F 5 95 FROSTED COVER 865 F 5 103 INCORRECT SCALE-RECORDER PAPER 600 F 5 103 INCORRECT SCALE-RECORDER PAPER 842 F 5 103 INCORRECT SCALE-RECORDER PAPER 845 F 5 107 POINTERS OBSCURE SCALE MARKS 632 F 5 157 LARGE MATRICES OF CONTROLS 865 F 8 157 LARGE MATRICES OF CONTROLS 881 F 8 157 LARGE MATRICES OF CONTROLS 882 F 8 213 LRG STRNGS/ MATRICES CONT / DISP 865 F 8 213 LRG STRNGS/ MATRICES CORT / DISP 881 F 8 213 LRG STRNGS/ MATRICES C0KT/ DISP 882 F 8 213 LRG STRNGS/ MATRICES CORT / DISP 902 F 8 O TABLE 3-11 (Cont'd)
SUMMARY
OF BACKPANEL HED's HED DESCRIPTION PANEL FIX MODIFY NONE NLTEG NO. 0700 SECTION 213 LRG STRNGS/ MATRICES CORT / DISP 970 F 8 215 SWITCH TO RECORDER ASSOCIATION 883 F 9 338 REG GUIDE 1.97 INSTR RANGE 883 F 5 362 FROSTED GLASS 614 F 5 362 FROSTED GLASS 800 F 5 362 FROSTED GLASS 811 F 5 362 FROSTED GLASS 842 F 5 362 FROSTED GLASS 883 F 5 362 FROSTED GLASS 907 F 5 369 SCALES HARD TO READ 625 F S 369 SCALES HARD TO READ 654 F 5 369 SCALES HARD TO READ 655 F 5 369 SCALES HARD TO READ 692 F 5 369 SCALES HARD TO READ 693 F 5 370 KEY OPERATED SWITCHES INAPPROP 631 F 4 370 KEY OPERATED SWITCHES INAPPROP 654 F 4 370 KEY OPERATED SWITCHES INAPPROP 655 F 4 370 KEY OPERATED SWITCHES INAPPROP 800 F 4 1009 RPS TRANSFER SWITCH HIDDEN 610 F 4 313 DUAL SCALE RECORDER 823 F D 5 108 POINTERS OBSCURE SCALE MARKS 669 F I 5 104 TIME HISTORY CAN'T BE SEEN 608 I 5 203 INCONSISTENT SRV LAYOUT 631 I 8 205 CCW CHILLERS ARRANGED A,C,B 904 I 8 88 INCONVENIENT BULB REPLACEMENT C22-P001 I 5 108 POINTERS OBSCURE SCALE MARKS 672 I 5 O TABLE 3-12
.O
SUMMARY
OF REMOTE SHUTDOWN PANEL HED's HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 5 ECCS/ SCRAM STA'11]S INFORMATION REMOTE S/D F 5 6 C0hTIRM INSTRU & CONT NEEDS REMOTE S/D F 4/5 49 J-HANDLE INADVERTENT OPERATION REMOTE S/D F 4 62 TASK ANALYSIS NOT DONE REMOTE S/D F 5 76 NO PROCESS UNITS ON LABELS REMOTE S/D F 5 78 W/L INDICATIONS INCONSISTENT REMOTE S/D F 5 80 INTERMEDIATE MARKINGS ON SCALE REMOTE S/D F 5 81 SCALE DIVISIONS OF 1,2 OR 5 REMOTE S/D F 5 89 NO SRV ACTUAL POSITION INDIC REMOTE S/D F 5 341 RHR VALVE TYPE INCONSISTENT REMOTE S/D F 4 342 RPV WATER LEVEL INSTR RANGE REMOTE S/D F 5 343 CST LVL INDIC NOT AVAILABLE REMOTE S/D F 5 61 REACTOR WL RECORDER RANGE REMOTE S/D F D 5 211 RHR/RCIC CONTROL ARRANGEMENT REMOTE S/D F D 8 340 TASK ANALYSIS "AS DESIGNED" REMOTE S/D2 F 4/5 O e O t k._
TABLE 3-13 O HED ASSESSMENT LISTING NED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO.- 0700 SECTION 1 OBSTRUCTED PADlWAY 601 F 1 1 OBSTRUCTED PATHWAY 805 F 1 2 EMERGENCY LIGHTING GENERIC F 1 3 ALTERNATE PROCESS UNITS 870 F 6 4 SOF'IWARE OUTPUT CHANGE COMPUTERS I 7 5 ECCS/ SCRAM STATUS INFORMATION REMOTE S/D F 5 6 CONFIRM INSTR & CONT NEEDS REMOTE S/D F 4/5 7 HULTI DIMENSION PLOT USABILITY PROCEDURE F 1 8 NO W/R RX PRESS RECORDER 680 F 5 9 CONT WATER LEVEL INDIC UNAVAIL MISSING F 5 10 NO FURNISHINGS REMOTE S/D F 1 11 SUPPORT COLUMN OBSTRUCTS VIEW MAIN AREA i 1 12 STORAGE SPACE - PROCEDURES NONE- F 1 13 STORAGE SPACE - PROCED & DRWGS REMOTE S/D F 1 14 STORAGE SPACE - SPARE PARTS NONE F 1 15 DEDICATED COMMUNICATIONS LINK NONE F 2 16 PANEL EDGES SHARP 680 F 1 17 RCIC CONTROLLERS OUT OF REACH REMOTE S/D F 1 F 0 18 HIGH CONTROLLER OBSCURES LABEL REMOTE S/D 19 ' SWITCHES TOO HIGH/ LOW 19 SWITCHES 700 HIGH/ LOW 601 604 I I 1 1 1 19 SWITCHES TOO HIGH/ LOW 632 I 1 19 SWITCHES TOO HIGH/ LOW 670 I 1 19 SWITCHES 700 HIGH/ LOW 671 I 1 19 SWITCHES TOO HIGH/ LOW 672 I 1 19 SWITCHES TOO HIGH/ LOW 800 I 1 19 SWITCHES TOO HIGH/ LOW 800 I 1 19 SWITCHES TOO HIGH/ LOW 865 I- 1 19 SWITCHES TOO HIGH/IDW 970 I 1 19 SWITCHES TOO HIGH/ LOW 970 I 1 19 SWITCHES TOO HIGH/ LOW REMOTE S/D F 1 20 CONTROLS /INDICAT TOO HIGH/IAW BACKPANELS I 1 21 CONTROLS / DISPLAYS TOO HIGH/ LOW REMOTE S/D F 1-22 LAYDOWN SPACE 680 F 1 23 GLARE AND PARALLAX ON PANELS VARIOUS I 1 24- GLARE / PARALLAX ON RECORDERS 600 I 1 24 GLARE / PARALLAX ON RECORDERS 642 I 1 24 GLARE / PARALLAX ON RECORDERS 680 I 1 24 . GLARE / PARALLAX ON RECORDERS 800 I .1 24 GLARE / PARALLAX ON RECORDERS 907 I 1 25 GLARE ON PANEL / INDICATORS REMOTE S/D F 1 26, MULTIPLE INPUTS (ANNUN) 601 1 3 26 MULTIPLE INPUTS (ANNUN) 680 I 3 26 MULTIPLE INPUTS (ANNUN) 845 I 3 26 MULTIPLE INPUTS (ANNUN) 870 I 3 4 TABLE 3 *.3 (Cont'd) HED ASSESSMENT LISTING MED DESCRIPTION PANEL FIX MODIFY NONE NUREG t No. 0700 SECTION 26 MULTIPLE INPUTS (ANNUN) 877 I 3 27 MULTIPLE INPLJT LPCS PRES ANNUN 601 I 3 28 ADEQUATE ANNUNC - ENTRY CONDIT GENERIC F 3 29 -PRIORITY COLOR CODE - ANNUNC GENERIC F 3 30 ANNUNCIATORS ABOVE CONTROLS 680 F D 3 i~ 30 ANNUNCIATORS ABOVE C0hTROLS 870 F D 3 4 31 ANNUNCIATOR PANEL LABELS GENERIC F 3 32 ANNUNCIATOR GROUPING /ARRANGMNT 601 F D 3 32 ANNUNCIATOR GROUPING /ARRANGMNT 680 F 3
-32 ANNUNCIATOR GROUPING /ARRANGMNT 800 F D 3 I 32 ANNUNCIATOR GROUPING /ARRANGMNT 904 D 3 33 ANNUNC NOT GROUPED BY TYPE GENERIC F 3
! 34 'ANNUN LGND PLATE REPLACE IDENT GENERIC F 3 ] 35 ANNUNC OUT OF SERVICE IDENT GENERIC F 3 36-- MISSING OR BLANK ANNUNC TILES VARIOUS F 3 37 SPECIFY ALARM INTENT VARIOUS F D 3 38 SUCCINCT WORDING - ANNUNCIATOR 601 F 3 38 SUCCINCT WORDING - ANNUNCIATOR 680 F 3 i 38 ~ SUCCINCT WORDING - ANNUNCIATOR 800 F 3 38 SUCCINCT WORDING - ANNUNCIATOR 870 F 3 39 INCONSIST ANNUNC ABBREVIATIONS 680. F D 3 39 INCONSIST ANNUNC ABBREVIATIONS 870 F D 3 40 ALPHA-NUMERIC CODE LABEL-ANNUN GENERIC F 3 41 SMALL ANNUNC LETTERING 680 F 3 42 3 DIFFERENT FONTS USED-ANNUNC 680 F 3 43 TEMPORARY LEGENDS - ANNUNCIAT 870 F 3 44 SEPARATE ANNUN ACKNWDG/ RESET- GENERIC F 3 45 ONLY 1 ANNUNC SILENT BUITON 680 F 3 46 DIFFERENT STYLE ANNUNC BUTTONS 680 F 3 47 DG-3 VOLT SWITCH MISSING 601 F 4 48 REACTOR MODE SWITCH MISSING 680 F 4 49 ~J-HANDLE INADVERTENT OPERATION REMOTE S/D F 4 50 TURB TRIP PB INADVERTENT ACTUA 680 F 4 51 MAN SCRAM /ISOLAT BUTTONS SAME 680 I' 4 52 THUMBWHEEL MOTION OPPOSITE GENERIC 1 4 , 53 NON-CONVENT MSIV SWITCH MOTION 601- F 4 i 54 SHAPE-CODED SWITCH HANDLES- GENERIC F 4 55 PUSH BUTTON COLOR STANDARD 601 F 4 55 PUSH BUITON COIDR STANDARD 870 F 4 55 PUSH BUITON COLOR STANDARD 680 F 4 56 ANNUN ACK/RFPT TRIP SIMILARITY' 680 F 4 l 57 INCONSIST DG WATTS /VARS METERS 601/877 I 5 58 DG3 RPM NOT AVAIL 601 1 5 59 REACTOR WL INDICATOR BE!4W TAF 601 F 5 p 60 VARIED SUPP POOL W/L REFERENCE GENERIC F 5 V TABLE 3-13 (Cont'd) HED ASSESSMENT LISTING MED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 61 REACTOR WL RECORDER RANGE REMOTE S/D F D 5 62 TASK ANALYSIS NOT DONE REMOTE S/D F 5 63 PSIA METERS NO LABELS / SCALES 680 F 5 64 BLANK METERS INSTALLED 680 F 5 65 NO DIRECT SRV POSITION INDICAT 601 F 5 66 ALTERNATE PROCESS UNITS 870 F 5 67 CST LVL UNITS INCONS W/PROCED 870 F 5 68 INADEQ SUP POOL LVL RANGE / ACCU GENERIC F D 5 69 NO SCALE ON RX PRESS METER 680 F 5 70 INCONS PRESS UNITS INSTR / TRIPS GENERIC F 5 71 INADEQ SUP POOL RANGE /ZERO POS 601 F D 5 72 RFP/MFP FLOW SCALES DIFFERENT 680 F 5 73 NO " AVERAGE" DW OR SP TEMP MISSING F 5 74 LOG SCALE INTERMEDIATE MARKS 907 F , 5 75 SMALL INDICATORS HARD TO READ 680 F 5 76 NO PROCESS UNITS ON LABELS 619 F 5 76 NO PROCESS UNITS ON LABELS 680 F 5 76 NO PROCESS UNITS ON LABELS 811 F 5 76 NO PROCESS UNITS ON LABELS 845 F 5 'O- 76 NO PROCESS UNITS ON LABELS 77- SCALES NOT MARKED OR UNCLEAR REMOTE S/D 823 F F 5 5 77 SCALES NOT MARKED OR UNCLEAR 842 F 5 78 W/L INDICATIONS INCONSISTENT REMOTE S/D F 5 79 RX W/L INSTR REFERENCES DIFFER GENERIC F 5 80 INTERMEDIATE MARKINGS ON SCALE -601 F 5 80 INTERMEDIATE MARKINGS ON SCALE 622 F 5 80 -INTERMEDIATE MARKINGS ON SCALE 623 F 5 80 INTERMEDIATE MARKINGS ON SCALE- 632 F 5 80 INTERMEDIATE MARKINGS ON SCALE 642 F 5 80 INTERMEDIATE MARKINGS ON SCALE 669 F 5 80 INTERMEDIATE MARKINGS ON SCALE 670 F 5 80 INTERMEDIATE MARKINGS ON SCALE 671 F 5 80 INTERMEDIATE MARKINGS ON SCALE 672 F 5 80 INTERMEDIATE MARKINGS ON SCALE 811 F 5 80 INTERMEDIATE MARKINGS ON SCALE 821 F 5 80 INTERMEDIATE MARKINGS ON SCALE 823 F 5 80 INTERMEDIATE MARKINGS ON SCALE 842 F 5 80 INTERMEDIATE MARKINGS ON SCALE 845 F 5 80 INTERMEDIATE MARKINGS ON SCALE 970 F 5 80 INTERMEDIATE MARKINGS ON SCALE . REMOTE S/D F- 5 81~ SCALE DIVISIONS OF 1,2, OR 5' 601 F 5 81 SCALE' DIVISIONS OF 1,2 OR 5 622 F 5
-81 SCALE DIVISIONS OF 1,2 OR 5 669 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 672 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 680 F 5 TABLE 3-13 (Cont'd)
ON/ COMPLETE HED LISTING HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 81 SCALE DIVISIONS OF 1,2 OR 5 800 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 821 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 823 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 842 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 870 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 904 F 5 81 SCALE DIVISIONS OF 1,2 OR S 970 F 5 81 SCALE DIVISIONS OF 1,2 OR 5 REMOTE S/D F 5 82 PRESSURE METER UNITS DIFFER 870 F 5 83 INCONS PUSHBUTTON COLOR CODE GENERIC F 4 84 COLOR CODE FOR NORM /ABN RANGE GENERIC F 5 85 DETECTING FAILED IND. LIGHTS GENERIC I 5 86 NO LAMP TEST CAPABILITY GENERIC I 5 87 DG-2 00S INDIC TILE NOT ETCHED 877 F 5 88 INCONVENIENT BULB REPLACEMENT C22-P001 I 5 89 NO SRV ACTUAL POSITION INDIC 601 F 5 89 NO SRV ACTUAL POSITION INDIC REMOTE S/D F 5 90 GREEN LIGHTS DIN 680 F 5 90 GREEN LIGHTS DIM 800 F 5
- .b i 90 GREEN LIGHTS DIM 881 F 5 90 GREEN LIGHTS DIM 882 F 5 91 REPLACEMENT OF TILES ERROR GENERIC F 5 92 BACKLIT PB & INDIC NOT DISTING 680 F 5 93 NO PAPER IN RECORDERS 601 F 5 93 NO PAPER IN RECORDERS 680 F 5 93 NO PAPER IN RECORDERS 870 F 5 94 RECORDER CHARTS HARD TO READ 601 F 5 95 FROSTED COVER 865 F 5 96 DUAL SPEED RECORDERS IDENF. GENERIC F D 5 97 POINT SELECT ON MULTIPOINT REC GENERIC I 5 98 MARK TO SHOW SIZE / TYPE PAPER GENERIC F 5 99' RECORDER INTERFERES W/ CONTROLS 680 F 5 100 RECORDER RANGE BANDING NORM /AB GENERIC F 5 101 INCORRECT WIDE RANGE W/L SCALE 680 F 5 102 ACTION LEVEL MARKING ON SCALES GENERIC F 5 103 INCORRECT SCALE-RECORDER PAPER 600 F 5 103 INCORRECT SCALE-RECORDER PAPER 842 F 5 103 INCORRECT SCALE-RECORDER PAPER 845 F 5 104 TIME HISTORY CAN'T BE SEEN 601 I 5 104 TIME HISTORY CAN'T BE SEEN 608 I 5 104 TIME HISTORY CAN'T BE SEEN 870 I 5 105 NO ALARM POINTS ON RECORDERS GENERIC F 5 106 INSTRUMENT HIGH DENSITY 680 F D 8 107 POINTERS OBSCURE SCALE MARKS 632 F 5 O
TABLE 3-13 (Cont'd)
\/ HED ASSESSMENT LISTING HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 107 POINTERS OBSCURE SCALE MARKS 680 I 5 108 POINTERS OBSCURE SCALE MARKS 669 I 5 108 POINTERS OBSCURE SCAIZ MARKS 672 I 5 108 POINTERS OBSCURE SCALE MARKS 691 D 5 108 POINTERS OBSCURE SCALE MARKS 694 D 5 109 UNLABELED INDICATING LIGHTS 669 6 109 UNLABELED INDICATING LIGHTS 672 F 6 110 FUNCTION LABELS MISSING VARIOUS F 6 111 SYSTEM LABELS ON PANELS VARIOUS F 6 112 PANEL NUMBER AND FUNCTION ids GENERIC F 6 113 DIFFICULT TO CORRELATE RX LVL 601 F 6 114 PEN COLOR ID NOT LABELED VARIOUS F 6 115 ESCUTCHEONS INCORRECT REMOTE S/D F 6 116 ISOL MATRIX LABELED BY # ONLY 601 I 6 117 NO LABELS ON LVL RECRDR/INSTRU 680 F 6 118 LABELS MISSING ON 3 CONTROLS 805 F 6 119 LABEL NOT DESCRIP.0F FUNCTION 805 F 6 120 MISSING PUSH-BUTTON LABEL 680 F 6 121 UNLABELED SELECTOR SWITCHES 883 F 6 p) -(_ 122 MISSING LABELS - ISOL VLV CONT 881 F 6 122 MISSING LABELS - ISOL VLV CONT 882 F 6 123 ANNUNCIATOR CONTROL NO LABEL 604 F 6 124 TURB TRIP / RESET NO LABELS 680 F 6 125 HIERARCHICAL LABELING NEEDED GENERIC F 6 126 REPETITIVE LABELING GENERIC F 6 127 PROJECTNG SWITCH OBSCURE LABEL VARIOUS T D 6 128 CONTROLLER LABEL PLACEMENT VARIOUS I 6 129 LABELS OBSCURED BY CONTR/ INSTR 680 F 6 130 INCONSISTENT LABELS 601 F 6 130 INCONSISTENT LABELS 631 F 6 131 VALVE' CONTROLS ONLY BY NUMBER 865 F 6 132 RCIRC HISLABELED AS "RCIC" 632 F 6 133 NAMEPLATE LABELS INCORRECT"1P" 870 F 6 134 CENTER POSIT MARKING CONFUSING 632 F 6 135 LABEL UNCLEAR 881 F 6 135 LABEL UNCLEAR 882 F 6 136 LABEL INCORRECT B21-F015 601 F 6 137 INCORRECT LABEL G33-R602 680 F 6 138 COND VAC TRIP RESET LABL VAGUE 680 F 6 139 NAMEPLATE LABELS REVERSED (N22) 870 F 6 140 N25-F120A(B),F125A(B) LABL WRG 870 F 6 I
141 ID NUMBERS REVERSED ON LABELS 870 F 6 142 RFPT OVERRIDE SWITCH MISLABEL 870 F 6 143 RFPT LUBE OIL TEST LABEL VAGUE 870 F 6 0 L
j- . TABLE 3-13 (Cont'd) HED ASSESSMENT LISTING HED . DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 144 1N22-F270 INCORRECT LABEL 870 F 6 145 1N33-C001A LABEL-WORD MISSING 870 F 6 146 IN62-F010 LABEL TOO VAGUE 870 F 6 147 1N22-F260A(B) MISLABELED 870 F 6 148 MISLEADING LABEL-STATOR PUMP 870 F D 6 149 ESCUTCHEONS WITH NO CONTROL 870 F 6 150 LABEL SYNTAX INCONSISTENT GENERIC F 6 151 INCONSISTENT TERMINOLOGY 601 F 6 151 INCONSISTENT TERMINOLOGY REMOTE S/D F 6 152 ABBREVIATIONS INCONSISTENT GENERIC F 6 153 LABELS WORDY GENERIC F 6 154 MISSING NAMEPLATES 669 F 6 154 MISSING NAMEPLATES 800 F 6 155 CENTER SWITCH POS LABL INCONSI GENERIC F 6 156 " AUTO" SHOULD BE " NORMAL" 680 F 6
'156 "AUT0" SHOULD BE " NORMAL" 870 F 6 156 " NORMAL" SHOULD BE "AtTT0" 870 F D 6 157 LARGE MATRICES OF CONTROLS 865 F 8 157. LARGE MATRICES OF CONTROLS 881 F 8 L O' . 157 LARGL MATRICES OF CONTROLS 882 F 8 158 SYS*lEM LOCATION AIDS LACKING REMOTE S/D F 6 159 LACK'0F DEMARCATION GENERIC F 6 160 SYSTEM GROUPING AIDS NEEDED MAIN AREA F 6 161 GROUPS-VS SUBGROUPS 680 D 6 161 GROUPS VS SUBGROUPS 845 F 6 1
161 GROUPS VS SUBGROUPS 865 F 6 161 GROUPS VS SUBGROUPS 881 F 6 161 GROUPS VS SUBGROUPS 882 -F 6 161 GROUPS VS SUBGROUPS 883 F 6 161 GROUPS VS SUBGROUPS REMOTE S/D F 6
;162 HIGH INSTR DENSITY / VISUAL CUES MAIN AREA F 6
! 163 HPCS DEMARCATION FROM DG 601 F 6 164 TURB TRIP / RESET COLOR CODE 7 680 F 6 c 165 MIMIC CONVOLUTED 601 F e 165 MIMIC CONVOLUTED 601 F 8 165 MIMIC CONVOLUTED 800 F 6 ? 165 MIMIC CONVOLUTED 904 F 6 i 166 MIMIC SHOWS SRVs IN SERIES' 601 F 6 167 MIMIC-ACCENTUATE MAJ ECCS FLOW 601 F 6 168 TEMP STRT/STOP POINTS ON MIMIC 601 F 6 169 COLOR CODE INCONSISTENT GENERIC F 6 170 MIMIC-MULTI USE OF WHITE DASH 601 F 6 171 BLUE MIMIC SHOULD BE GRAY 800 F 6 lO 4 HED ASSESSMENT LISTING HED DESCRIPTION PANEL FIX N0DIFY NONE NUREG
' NO . 0700 SECTION 172 NEED MORE FLOW ARROWS 904 F 6 173 MIMIC NEEDS FLOW DIRECTION 870 F 6 174 TEMPORARY MIMICS W/ TAPE 601 F 6 175 POOR MIMIC FOR SUPP POOL 601 F 6 176 MIMIC START /END POINTS VAGUE 800 F 6 176 MIMIC START /END POIhTS VAGUE 970 D 6 177 SOFWARE CHANGE ADMIN ADMIN F 7 178 SECURE STORAGE OF SOFWARE ADMIN F 7 179 ALARM ACKNOWLEDGE TOO GENERAL COMPUTERS F -7 180 PLANT / COMP ABBREV INCONSISTENT COMPUTERS 7 7 181 UNNECESSARY GRAPHIC FUNCTIONS 'COMPWERS s' 7 182 ENGRAVED LABELS / TEMP LABELS COMPUTERS F 7 183 PROCESS COMP FAILURE PROCEDURE ADMIN F 7 184 NO CROSS INDEX FOR DATA POINTS COMPWERS F 7 185 HARD TO DISTINGUISH C,0,0,G,D COMPUTERS I 7 186 CONFUSING EhTRY FORMATS COMPWERS F 7 187 CRT PAGE SPACING (TOP & BOTTOM) COMPUTERS F 7 188 CRT COLOR USE NON-STANDARD COMPWERS F 7 189 CRT COLOR CODING INCONSISTENT COMPUTERS F 7 O 190 PRIhTOUT NOT PRIORITIZED 191 NO HIGH SPEED PRIhTING COMPUTER COMPWERS F
F 7 7 192 REMOTE PRINTING NOT CONFIRMED COMPWERS I 7 193 PRIhTER PAPER SUPPLY COMPWERS F 7 194- NO PRINTOUT ANNOTATION SURFACE COMPWERS F 7 195 PRINTER OFF FOR PAPER RELOAD COMPWERS F 7 196 PAPER / RIBBON CHNGE INSTRUCTION COMPUTERS F 7 197 RPV LVL NOT NEAR HPCS CONTROLS 601 I 9 198 HIGH DENS /SML INSTR-RX W/L 680 F D 8 199 DW TEMP N/A NEAR REFERENCE LEG MISSING F 8 200 ILLOGIC ISOL STAT TILE GROUPNG 601 F 8 201 INNAPPROP LRG/ CIRC RFPT METERS 680 F 4/5 202 SRV CONTROL ARRANGEMENT 601 F 8 203 INCONSISTENT SRV LAYOUT 601 I 8 203 INCONSISTENT SRV LAYOUT 628 D A 203 INCONSISTENT SRV LAY 0ttr 631 I 8 204 INCONSIST VALVE CONTROL LAYOLTT 601 F 8 205 CCW CHILLERS ARRANGED A.C.B 904 I 8 206 CONDENSATE INLET VLV ARRANGMNT 870 I 8 207 INCONSIST RCIC DOS ARRANGEMENT 601 I 8 208 INCONSIST LAYOUT FOR DIV1/DIV2 601 I D 8 209 SLC DIVIDED BWN PANEL 8 601 I 8 210 DW PRESS & TEMP NOT ADJACENT 601 F 8 211 RNR/RCIC CORTROL ARRANGEMENT REMOTE S/D F D 8 212 LONG STRINGS OF METERS 601 F 8 O 3 TASLE 3-13 (Cont'd) O .ED mmMm tm. MED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION
, 213' LRG STRNGS/ MATRICES CONT / DISP 865 F 8 213. LRG STRNGS/ MATRICES COE/ DISP 881 F 8 213 LRG STRNGS/ MATRICES COE/ DISP 882 F 8 213 LRG STRNGS/ MATRICES COE/ DISP 902 F 8 213 LRG STRNGS/ MATRICES COE/ DISP 970 F 4 213 LRG STRNGS/ MATRICES CO E/ DISP 628- D 8 213 LRG STRNGS/ MATRICES CONT / DISP 631 D 8 213 LRG STRNGS/ MATRICES CONT / DISP 902 D 8 213 LRG STRNGS/ MATRICES CONT / DISP 906 D 8
, 214 SWTCH/ CONTROL RELATION UNCLEAR REMOTE S/D F 6 215 SWITCM TO RECORDER ASSOCIATION 883 F 9 216 RX PRES /SRV CONT NOT ADJACEE 601/680 F 9 300 ANTMROP0 METRIC MEASURE 904 I 1 301 NO FEEDBACK FOR ISOL SYSTEM 655 F D 6 302 INDICATIONS / MIMICS INTEGRATION REMOTE S/D F 6 303 ECC WATER MIMIC COLOR WRONG 601 F 6 304 CONTROL FEEDBACK NOT AVAIL 654 F D 6 305 MIMIC /DEMARCAT CHANGES NEEDED 800 F 6 306 RRCS FEEDBACK ON DIFFER PANEL 680/C22-P001 F 9 307 MIMIC ARROWS NOT STANDARD 808 F 6 308 SYMBOLS VS ARROWS ON MIMIC 904 F 6 309 LABELS OBSCURE INFO 600 F 6 309 LABELS OBSCURE INFO 612 D 6 309 LABELS OBSCURE INFO 614 F 6 309 LABELS OBSCURE INFO 811 F 6 309 LABELS OBSCURE INFO 823 F 6 309 LABELS OBSCURE INFO 842 F 6 309 LABELS OBSCURE INFO 865 F 6 309 LABELS OBSCURE INFO 883 F 6 309 LABELS OBSCURE INFO 907 F 6 310 EXTRANEOUS INFORMATION 601' F. 6 310 EXTRANEOUS INFORMATION 680 1 6 310 EXTRANEOUS INFORMATION 800 I 6 310 EXTRANEOUS INFORMATION 807 I A 310 EXTRANEOUS INFORMATION 808 I 6 310 EXTRANEOUS INFORMATION 409 I 6 310 EXTRANEOUS INFORMATION '811 I 6 310 EXTRANEOUS INFORMATION 823 I 6 310 EXTRANEOUS INFORMATION 842 I 6 310 EXTRANEOUS INFORMATION 845 I 6 310 EXTRANE0US INFORMATION 846 I 6 310 EXTRANEOUS INFORMATION 865 I 6 310 EXTRANEOUS INFORMATION 868 I 6 310 EXTRANEOUS INFORMATION 869 I 6 310 4XTRANEOUS INFORMATION 883 I 6 i .
TABLE 3-13 (Cont'd)
~-
HED ASSESSMENT LISTING HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 310 EXTRANEOUS INFORMATION 902 I 6 310 EXTRANEOUS INFORMATION 904 I 6 310 EXTRANEOUS INFORMATION 906 I 6 310 EXTRANEOUS INFORMATION 907 I 6 310 EXTRANEOUS INFORMATION 969 I 6 311 MIMIC LACKS HEAT EXCHANGER 800 F 6 312 DUAL SCALE METER 868 F 6 312 DUAL SCALE METER 869 F 6 313 DUAL SCALE RECORDER 823 F D 5 314 PROCESS UNIT LIST VARIOUS F D 5 315 CRT - HARD COPY-SOME, NOT ALL PROCESS COMP I 7 316 KEYBOARD NOT STANDARD STYLE PROCESS COMP I 7 317 CRT GLARE FROM WHITE TABLE TOP PROCESS COMP I 7 318 INSUFFICIENT MESSAGE HIGHLIGHT PROCESS COMP F 7 319 SCRAM TRIP ANNUNC LABEL WRONG 680 F 3 320 COMP PROCEDURES NOT IN PLACE ADMIN I 7 320 ERIS PROCEDURES NOT IN PLACE REMOTE S/D I 7 321 SPARE PARTS NOT AVAIL REMOTE S/D F 1 322 MULTIPLE ANNUNC FOR MSIV RAD 680 F 3 (q) 323 APRM/IRM RECORDER PAPER SCALE 680 F 5 324 NO SINGLE SCRAM ANNUNCIATOR GENERIC F 3 325 NO AVG SUPP POOL TEMP INDICAT HISSING F 5 326 NON-STAND USE OF AMBER LIGHT 601 F 5 327 NO SINGLE INDICATOR FOR 5% PWR 680 F 5
'328 GENERATOR BREAKER MIMIC WRONG 680 F 6 329 NO TURBINE TRIP INDICATION MISSING F 3 330 FUSE IDENTIFICATION POOR 691 F 6 330 FUSE IDENTIFICATION POOR 692 F 6 330 FUSE IDENTIFICATION POOR 693 F 6 330 FUSE IDENTIFICATION POOR 694 F 6 331 RELAY CONTACT ID & ACCESS POOR 618 F 6 331 RELAY CONTACT ID & ACCESS POOR 618 F 1 331 RELAY CONTACT ID & ACCESS POOR 629 F 1 331 RELAY CONTACT ID & ACCESS POOR 629 F 6 332 NO SINGLE BOP ISOL INDICATION MISSING F 3 333 RPV PRESS. RECORDER READABILITY 680 F 5 334 NO SIMPLE INDIC OF MSIV LOGIC MISSING F 3 335 NO RCIC AUTO START LOGIC INDIC MISSING F 3 336 NO ADS TIMER EARLY WARNING HISSING F 3 337 SUPP POOL HI TEMP ANNUNC MATRX 601 F 3 338 REG GUIDE 1.97 INSTR RANGE 601 F 5 338 REG GUIDE 1.97 INSTR RANGE 883 F 5 339 RPV LVL 1 ANNUNC LEGEND WRONG 601 F 3 O
v
TABLE 3-13 (Cont'd)
;O MED ASSESSMENT LISTING ED DESCRIPTION PANEL FIX MODIFY NONE NUREG ND. 0700 SECTION 340 TASK ANALYSIS "AS DESIGNED" REM m 8/D2 F 4/5
, 341 RNR VALVE TYPE INCONSISTENT REMOTE S/D F 4 342 RPV WATER I2 VEL INSTR RANGE REM m 8/D F 5
'343 CST LVL INDIC NOT AVAILABLE REMOTE S/D F 3 344 SML INSTR-COMPLICATED CONTROLS 680 I 4 344 SML INSTR-COMPLICATED CONTROLS 680 I 6 345 NO MECHANICAL STOP-RFP B CONTR 680 F 4 346 STORAGE RACK LOCATION 805 F 1 347 COLOR CODE PEI BINDERS MAIN AREA F 6 348 FUSE PULLER AVAILABILITY MISSING F 1 349 RX PRES METER GROUPNG CONFUSES 680 F 8 350 PHONES di HEADSET JACKS GENERIC F 2 351 STORAGE AT So DESK 805 F 1 352 PC KEYSOARD VS DIRT 805 I 7 353 STROKE VALVE IDENTIFICATION GENERIC F , 4 354 "CLOSE/0 PEN" VS "0 PEN /CLOSE" 870 F 4 355 ANNUNCIATORS 700 SMALL 680 F 3 356 CHART RECORDER PEN LAYOUT VARIOUS F 9 357 BRKR CONTROL SWITCH INADV ACW 870 -F 4 O 358 UNCLEAR MIMICS 359 MIMIC UNCLEAR 870 601 F
F 6 6 359 MIMIC UNCLEAR 655 F 6 360 : EQUIP NOT YET INSTALLED VARIOUS F 1 361 NAMEPLATE / LABEL LIST VARIOUS T I 6 362 FROSTED GLASS 601 F 5 362 FROSTED GLASS 614 F 5 362 FROSTED GLASS 400 F 5 362 FROSTED GLASS all F 5 342 FROSTED GLASS 442 F $ 362 FROSTED GLASS 483 F 5 362 FROSTED GLASS 907 F 5 363 RANGE LIST, INDICATOR SCALES VARIOUS F 5 364 SCALES NON-STANDARD LIST. VARIOUS F 5-365 ISOLATION MATRIX 601 F 5 364 ANN 0YING ANNUNC AUDITORY ALARM GENERIC F 3 367 C91 TERMINAL KEYBOARD STICKS PROCESS COMP F 7 368 RESPIRATOR COMMUNICATION POOR NONE F 2 369 BCAI25 MARD M READ 625 F 5 349 SCALES RARD TO MAD 654 F 5 369 SCA!AS MARD M READ 655 F 5 369 SCALES MARD M READ 692 F 5 369 SCALES MARD TO READ 493 F 5 370 XEY OPERAND SWITCMS INAPPROP 601 F 4 370 REY OPERATED SWITCM S INAPPROP 640 F 4 O 8
,m_.m.---- m. -
.4 . . . m . , . _ . _ - . _ . _ . . . ~ __
TASLE 3-13 (Cont'd)
~O E D ASSESSMEE LISTING NED DESCRIPTION PANEL FIX MODIFY NONE NUREG ND. 0700 SECTION 370 REY OPERATED SWITCHES INAPPROP 631 F 4 370 KEY OPERATED SWITCHES INAPPROP 654 F 4 370 KEY OPERATED SWITCHES INAPPROP 655 F 4 370 KEY OPERATED SWIK E S INAPPROP 400 F 4 371. INADEQUATE LIGNTING REM 017. S/D F 1 1001 RFSP CO UROLS N W NEAR ANNUNC 870 F 9 1001 RFSP CONTROLS N W NEAR ANNUNC 680 F 9 1002 SLC 008 ALARMS WHEN WORKING 601 F 3 1003 MULTI INPUT-RADWASTE TRSL ALRN 680 F 3 1004 CHILLER ALARMS NUISANCE 800 F 3 1004 CHILLER ALARMS NUISANCE 904 F 3 1005 PAGE PHONE LOCATIONS INSUFF MAIN AREA F 2 1006 PLANT PAGE MESSAGES DISTRACTNG GENERIC F 2 1007 SLOW SPEED TYPER PROCESS COMP F 7 1004 WATER TREATHE SLDG ALRN MASK REMOTE PANEL F 3 1009 RPS TRANSFER SWITCH HIDDEN 610 F 4 1010 E51-F063 SWTCH LACKS AUTO POSI 601 F 4 1011 VLV SWCH NAMLPLATES NORM /AUM VARIOUS F 6 1012 VLV SWTCH NAMEPLATES OPEN/AWO VARIOUS F 6 1013 RPV SIPHON NUISANCE ALARM 601 F-O 1014 COMMUNICATION TO REMOTE PANELS REMOTE PANEL F 1015 NAMEPLATE DISCREPAN0Y 881 F 3
2 6 1016 DC SUS UNDERVOLTAGE ALRN IAGIC 877 F 3 1017 INDICATING LIGHTS SELOW COURL 870 F 9 1018 MAN ISOL SWTCH ARMED ALARMS 601 F 3 1019 SATELLITE ANNUNC ALARM LOGIC GENERIC I 3 1020 SOC DIGITAL WINDOW USEFULNESS 640 F 5 1021 .H2 ANALYZER ALARMS LOGIC 870 F D 3 1022 INCONSISTENT VAC/ PRES UNITS GENERIC F 5 1023 ANNUNC NOMENCLTR-RCIC/RNR ISOL 601 F 3 1024 CONS GAS DW PURGE VLV NA'fEPLTS 800 F 6 1025 ECC PUMP OVERIDE-NO AMSER LITE 401 F 5 1026 FCV CAVITATE INDIC L111 IAGIC - 640 F 5 1027 XFMER DISCONNECT INADV ACTUATE. 680 F 4 1028 NON STAND GREEN PERMISIV LIGHT 640 F 5 1029 CAD CONDUCTVTY RECRDR IACATION 870 F 9 1030 NON STAND ANSER PERMISIV LIGNT 680 F 5 ' 1031 INSUFF IVACUATION~ ALARMS MISSING F 3 1032 N11 823 SPRING RETURN /8HAPE 470 F 'D 4 1033 RFFT TRIP ANNUNC NUISANCE ALRN 680 F 3 1034 ECCS PUMP TRIP ALARM PRIORITY 601 F 3 1035 SUPP P0OL M/U NUISANCE AIARM 601 F 3 1036 TURS FIRST STAGE SCALE UNITS 680 F 5 1037 -RX LVL CONTROLLER ARRANGEME N 640 F 6 3
m TABLE 3-14 HED VERIFICATION LISTING HED DESCRIPTION PANEL FIX MODIFY NONE NUREG NO. 0700 SECTION 400 TOO MANY SUPR POOL LVL RANGES 883 F 8 401 STATOR WATER C00 LNG TIME DELAY 870 F 4 402 CNTMT/DW VS DW/CNTNT DIFF PRES 601 F 5 403 DEMARC & HEIRARCH LABEL NEEDED 870 F 6 404 NO SECTION NUMBERS -BENCHBOARD 601 F 6 404 NO SECTION NUMBERS -CONSOLE 680 F 6 404 NO SECTION NUMBERS -BENCHBOARD 870 F 6 405 INCONSISTENT VALVE SYMBOLS 601 F 6 405 INCONSISTENT VALVE SYMBOLS 680 F 6 406 UNNECESSARY STRAINER SYMBOLS 601 F 6 407 NO ESW CONNECT ON RHR B MIMIC 601 F 6 408 REHEATER DISPLAY GROUPINGS BAD 870 F 8 O l 0 4.0 IMPLEMENTATION - s The complete Detailed Control Room Design Review identified 334 HED's. 299 HED's (89.5%) are to be completely corrected, 16 HED's (4.8%) are to be partially corrected, and 19 HED's (5.7%) are to be left uncorrected.1 Implementation schedules for verified Human Engineering Deficiency improve-ments are documented in the Correction Schedule section of the HED Report Sheets, Attachment I. Two dates are provided in this section: o Planned Completion - The milestone date for completion of the HED improvement. Two milestone dates are used: Fuel Load, and Prior To Start-up After First Refuel, o Vork Complete - The date the HED improvement was verified complete in the field. Of the 315 HED's designated as Fix or Modify, 297 HED improvements (94%) are 7- scheduled for complete implementation by Fuel Load. Design work remains to x- be completed on 20 of these HED's, many of which were identified in the final months of the review. If any HED improvements scheduled for completion by Fuel Load are delayed, each one will be identified, evaluated and justified to the staff with a revised impicmentation schedule. The remaining 18 HED's improvements (6%) with a deferred schedule of Prior To Start-up After First Refuel due to scheduling or information restrictions are listed in Table 4-1 and have been assessed as not being associated with either a safety or an operability consequence. A summary of the deferred HED
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improvements are: o Indicator scale modifications associated with 9 HED's (HED 72, 74, 77, 80, 81, 107, 313, 314, 364). 8 For this numerical overview the highest implementation was taken for HED's with more than one implementation classification. o Scale t inge and limit color banding enhancements associated with 5 HED's (HED 84, 100, 102, 363, 369). At fuel load temporary i ) v' improvements will provide normal range and important limits on the indicator covers where appropriate. As system operating information and setpoints are established, the permanent color banding will be applied to the scale. o The generator electrical mimic (HED 318). Mimic will be temporarily improved by fuel load and corrected later by moving an indicating light. o The checklist item F7.1, control room noise level survey. Survey will be j evaluated when the carpeting is installed after fuel load (HED 360). o The rearrangement of vertical displays on the reheat steam se-tion of P870 (HED 408). o The new keylocked control switch design (HED 370). The new design intent to have all keys (except the reactor mode switch) removed 3- during full power operating will be partially accomplished by fuel (b load by administrative control. A procedure will require all keys be removed from vertical panels when not in use to avoid the inadvertent bumping. The administrative control adequately improves the deficiency until the designated 70 keylock switches are replaced with conventional controls.
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4 t TABLE 4-1 HED CORRECTION SCHEDULE PRIOR TO START-UP AFTER FIRST REFUEL OLTTAGE HED NO. DESCRIPTION 72 Feedwater flow scales use different multipliers 74 Log scales lack intermediate markings 77 Scales on P823 and P842 are not identified clearly 80 Indicators have greater than 9 intermediate graduations 4
- ' - all indicators except R.G. 1.97 indicators 81 Scale divisions are not in multiples of 1, 2, or 5
- all indicators except R.G. 1.97 indicators
-84 Provide applicable color banding on indicators 100 Recorder scale color banding 102 Indicator scale limit /setpoint color banding 107 P632 leak detection flow meter pointers (4) require shortening 313 P823 VIB & ECC recorder need process unit label "ECC"
, . deleted 314 Process unit PSI changes PSIG - all panels 0[ 328 Generator mimic correction %* p p
-360 Survey control room noise level
- 363 Color code indicator scales for consistent and meaningful usage where applicable 364 Scale divisions do not conform to standard - P680 369 Color code appropriate meter scales on P625, P654, P655, P692 and P693-(subset of HED-363) 370 Replace. inappropriate keylocked switche=
408 Rearrange reheat steam displays on P870 p '
5.0 ON GOING HUMAN FACTORS PROGRAM
/~'T The PNPP Human Factors Program is committed to review Human Engineering Observations and resolve Human Engineering Discrepancies over the life of the plant. For the past 3 years the PNPP Human Factors Unit has monitored design changes affecting control room and remote shutdown panels. The design changes
.were reviewed by the Human Factors Unit and revised as necessary for proper integration into the control room.
A PNPP Design Procedure has been developed to ensure that a Human Factors Design Review is performed on design changes that affect the control room or remote reactor shutdown system interfaces. The procedure can be referenced in Attachment O. The Human Factors Unit has documented the PNPP Control Room Standards (Attachment N) that were established to evaluate Control Room design changes. This document will be maintained and updated over the' life of the plant. Revision 1 of the PEI's will be submitted to the NRC in the Procedure Generation Package. This PEI revision and subsequent revisions will be: reviewed by the Human Factors Unit using the Task Analysis Procedure to ensure all operator tasks are analyzed. The human factors dynamic validation of the . A'() control room to confirm operator performance, beyond the requirements of NUREG 0737 Supplement 1, will be conducted in conjunction with the PEI Validation Plan during the spring of 1985. e i v _ _ _ . _ . _ _ - . _ , . . _ . . . , _ . , . - _ _ . . ~ . . _ _ . . , ___ _ -
I 6 . 01 . CONCLUSION
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j l \-> - In-conclusion the PNPP Detailed Control Room Design Review (DCRDR) Program i accomplishes'the following objectives: l o The DCRDR Program meets and exceeds the requirements set forth in NUREG-0737 Supplement 1. o The results of the DCRDR show that the ability of the PNPP control room
$ operators is improved'to prevent or cope with accidents by improving the information provided them.
t d' o The PNPP management commitment to the On Going Human Factors Program ensures that the DCRDR objectives will~ be maintained over the life of the t
;. plant.
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