ML20114D437
| ML20114D437 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/10/1985 |
| From: | Bunker R BWR OWNERS GROUP |
| To: | |
| Shared Package | |
| ML20114D418 | List: |
| References | |
| NUDOCS 8501310313 | |
| Download: ML20114D437 (24) | |
Text
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l~ BWROG HUMAN FACTORS ENGINEERING - CONTROL ROOM SURVEY SUPPLEMENT l r i i 1 .- 1 1 4 M- ) i ? 4 I h !:0 ^ 4 n 1 t K s N t i i r
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1 p 5-m 8~ ATIACHMENT C L {. BWR OWNER 5 GROUP CONTROL 500M DESIGN REVIEW COMMITTEE HUMAN FACTORS ENGINEERING 2 CONTROL ROOM SURVEY l [! SUPPLEMENT l~ e E. l r l. L. K i . r-e . El . -
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(N BWR OWNERS' GROUP CONTROL ROOM DESIGN REVIEW COMMITTEE 1 HUMAN FACTORS ENGINEERING CONTROL ROOM SURVEY O SUPPLEMENT
. Prepared by:
Ronald S. Bunker Date General Electric Company , Reviewed by: G. R. Mullee Date General Electric Company Approved by: A. Migas Date Chairman, Control Room Design Review Committee
- BWR Owners' Group
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r t f(q-i s./ CONTROL ROOM SURVEY SUPPLEMENT TABLE OF CONTENTS fage,
' INTRODUCTION 3 CHEGLISTS SA. Panel Layout and Design 5 SB. Instrumentation and Hardware 9 SC. Annunciators 12 SD. Computers 13 SE. Procedures 16 SF. Control Room Environment 17 SG. Maintenance and Surveillance 21 O Table I CRS Program Modifications 4 2 --
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l mygy .. This supplement is intended to augment Revision 1 of the BWR Owners Group Control Room Survey (CRS), Program dated 1/1/81. It is to be included as part of the Control Room Review Checklists (Section III of the CRS Program) to further document proposed ' control room enhancements. The additional items listed in the supplement have been drawn from human engineering guidelines I recommended in NUREG-0700 and verified through considerable experience of Owners Group Survey teams. Major sections of the supplement checklists are identified by letters corresponding to section designations used in the original checklists. In order to differentiate between the two numbering systems, an "S" prefix has been assigned to each supplement item. i The CRS Supplement is to be implemented in accordance with the methodology [ discussed on page 15 of the CRS package. As before, Sections SA, SB, and SC are to be completed for each panel containing controls and displays normally operated by control room operators. The remaining sections apply to the entire control room and therefore need to be completed only once. Sections A, B, and C should also be completed for the remote shutdown panel. In addition to the attached checklist supplement, several other modifications have been adopted in the CRS Program. These are listed in Table I. All other l aspects of the program remain uncharged. i .t O
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TABLE I
,CRS PROGRAM MODIFICATIONS The following modifications have been implemented in the BWR Owners Group Control Room Survey Program:
e Sections A, B, and C of the Control Room Review Checklists are to be performed for the remote shutdown panel in addition to those panels previously recommended. e A supplement (attached) has been added to the Control Room Review Checklists.
-- e Task analyses and walkthroughs are performed based upon symptom oriented emergency procedures developed from the BWR Owners Group Emergency Procedure Guidelines. If plant-specific procedures are not yet available, the guidelines themselves should be utilized in the analysis. In this case, existing procedures for a scram, relief valve failure, and loss of coolant accident should also be evaluated.
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g pg CONTROL ROOM REVIl!N SUPPLEMENT Panel tV SA PANEL LAYOUT AND DESIGN SA1 Anthropometrics SA1.1 Is seating area adjacent to desks 4 3 2 1 0 x 1 = and sit-down consoles sufficient to allow the operator to get into and out of a chair easily and to turn in the chair to view the equipment behind (30" lateral space, 36" between desk and opposing panel or surface)? S sal.2 Is sufficient space allowed between 4 3 2 1 0 x 2 = the panel and opposing surf aces such that the operator may perform required tasks without hindrance? 4 sal.3 If the operator is required to see over 4 3 2 1 0 x 2 = a stand-up console, does the console height not exceed 58 inches? SA2 Control Room Iayout S A2.1 Does the location of the shif t 4 3 2 1 0 x 2 = supervisor's office permit prompt p access to the control room under all conditions? h
[(' Panel SA2.2 Are operator's desks and chairs 4 3 2 1 0 x 1 = comfortable and in good repair? e SA2.3 For a multi-unit plant, are senior 4 3 2 1 0 x 2 = operators who supervise or assist in the operations of more than one unit stationed such that they may communicate effectively with all operators and view each control board?
'( ) SA2.4 Are operators provided with 4 3 2 1 0 x 1 =
sufficient desk and working space for performance of required tasks? SA3 Control / Display Grouping Is the association of feedback 4 3 2 1 0-x 3 = indication to related controls made readily apparent through labeling, sim,ics, demarcation lines or position?
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n.. Panel SA4 labels =
- 4 3 2 1 0 x 2 SA4.1 Where abstract symbols are used, ..
are they of standard configuration. distinguishable from other symbols, and consistent in use within and across panels? E 3 = 4 3 2 1 0 x SA4.2 Are labels located such that they do not cover or detract from other necessary information? g O SA4.3 Is extraneous information not included 4 3 2 1 0 x 1 = (e.g. , manuf acturer's trademark, patent notice,etc.)? SAS Unit Integration 3 = For a multi-unit plant, are alarms 4 3 2 1 0 x SA5.1 f or shared plant systems duplicated in all control rooms? 2 = For multi-unit plants, if equipment 4 3 2 1 0 x SAS.2 is shared between control rooms, is there administrative control over use of the equipment? h
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i l c e,.. l 'O " ' Panel l l l SA5.3 Is the status of shared equipment 4 3 2 1 0 x 3 = l displayed in each control room? I I i O L ..O- .
4 Panel SB INSTRUMENTATION AND HARDWARE
$31 . Indicators i SBl.1 Are indicator scales easily read when 4 3 2 1 0 x 3 =
stationed at the panel? i 4 l SBl.2 Is the use of multiscale and logarith- 4 3 2 1 0 x 2 = mic scale indicators minimized?
- SBl.3 Are displays which reflect only a 4 3 2 1 0 x 3 =
demand signal labeled accordingly? l l SBl.4 Are process units and multipliers 4 3 2 1O x _3 = specified? l SBl.5 Are drum-type counters readable from 4 J 2 1 u.x J = i the normal viewing position? l t i ?- O t
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Panel f SBl.6 Are digital displays readable from 4 3 2 1 0 x 3 = the normal Vievirs position? SB2 Recorders SB2.1 Is all recorder information visible 4 3 2 1 0 x 2 = j through recorder windows (i.e. t- open-door operation not required)? < - SB2.2 Do multi-channel recorders clearly 4 3 2 1 0 x 2 = display the channel being plotted? SB3 Indicating Lights Have procedural or design provisions 4 3 2 1.0 x 2 =_ been implemented to prevent inter-i changing indicating light lenses? O
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4 Panel SB4 Switches SB4.1 Where contig'uous legend pushbuttons 4 3 2 1 0 x 3 = l are _used, are barriers provided ^ to prevent inadvertent actuation of adjacent pushbuttons? SB4.2 Are key-operated switches used 4 3 2 1 0 x 2 = only where appropriate (i.e. , to prevent unauthorized control actuation)? O 4 4-d J i r O
7 G Pane 1 SC ANNUNCIA1DRS l SC1 Window Design - Is the density of annunciator
. matrices such that the operator 4 3 2 1 0 x 3 =
usy quickly ascertain a window l position? SC2 Acknowledgement Are annunciator response controls 4 3 2 1 0 x 2 = j coded for ease of recognition (color, shape, demarcation, etc.)? i o 12 -
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i - l DSD COMPUTERS I SD1 Console SDI.1 Do typewriter keyboards conform to the 4 3 2 1 0 x 1 = standard "QWERTY" atrangesent? SD1.2 Do numeric keyboards conform to either 4 3 2 1 0 x' 1 = the " telephone" style' or the " calculator" style arrangement? SD1.3 Do function keyboards contain only 4 3 2 1 0 x 1 = those keys which are used by the O'
. operators (i.e. no irrelevant keys such as used by programmers)?
SD1.4 Are function controls segregated 4 3 2 1 0 x ~lI" = from alpha numeric keys? SD1.5 Are function controls clearly . 4 3 2 1 0 x. 2= labeled to indicate their function?. 13 -
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SD2 Capability SD2.1 Is computer use and software access 4 3 2 1 0 x 2 = administrative 1y controlled? SD2.2 Is the system designed such that data 4 3 2 1 0 x 2 = is not lost during printer down ecriods? s SD3 CRTs SD3.1 Are CRTs free from glare and easily 4 3 2 1 0 x _2 = readable from normal viewing positions? 0: SD3.2^ Are messages which require immediate 4 3 2 1 0 x "lI~ = operator response highlighted to attract the operator's attention? 1 SD3.3 Are prompts and error messages used 4 3 2 1-0 x _2 = to guide the operator in proper system operation? .l Are abbreviations, acronyus, and
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SD3.4 ~ 4 3 2 1 0 x 2 = synonyms used consistent with
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those used elsewhere in the control room?
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' SD4 Printers SD4.1 Are printers located in a, readily 4 3 2 1 0 x 1 =
accesible area in the control room? SD4.2 Do printers have the capability 4 3 2 1 0 x 1 = to record alarm, trend, and plant status data? + SD4.3 Is the system capable of providing a 4 3 2 1 0 x 1 = hard copy of any page appearing on the CRI?
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D SE PROCEDURES SE1 Are procedures, reference materials and other documents readable (i.e. not 4 3 2 1 0 x 3 = dirty, torn dog-eared or otherwise difficult td read)? SE2 Is a set of computer operating procedures available in the control 4 3 2 1 0 x 2 = room describing the computer system, ' procedures necessary to accomplish operator-computer interface functions and contingency actions in the event of a computer f ailure? i l l' l r i .. l l l i - L
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SF CONTROL ROOM ENVIRONMENT SF1 Communications SF1.1 Are periodic maintenance tests per- 4 3 2 1 0 x 2 = , formed on all communications sytems? SF1.2 Is sufficient communications equipment 4 3 2 1 0 x 2 = (cords, jacks, etc.) provided in well marked locations? SF1.3 Is an intercom system provided con- 4 3 2 1 0 x 2 = necting the control room with i
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the shif t supervisor's office? SF1.4 Are instructions provided for the 4 3 2 1 0 x 2 = l use of all communications systems? I l l SF1.5 'Are operators trained in the use 4 3 2 1 0 x 3 = of all communications systems? l l l l l
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ST2 Lighting ' -~~ - - ~ -- - - - - - -
; SF2.1 Are illumination levels at operator 4 3 2 1 0 x _3 =
desks adequate for the tasks being performed (50 footcandles minimum, 100 footcandles maximum, 75 foot-candles recommended)? cH49&E R E CO M MY. N b Eb SF2.2 Is illumination uniform over a given 4 3 2 1 0 x 2 = vork station and from one station to another? SF2.3 Is shadowing avoided on panels and 4 3 2 1 0 x 2 = other operator work areas? SF2.4 Have direct sources of glare been 4 3 2 1 0 x _2 = avoided (e.g. light emitted from displays and indicators)? i r \ t i l t !O 6- ._ . - - - - - . . . - - . -
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' - SF3 Emergency Response Equipment ~ ~ ~ ~
S F3.1 Is operator protective equipment 4 3 2 1 0 x _2 = periodically checked?
-SF3.2 Is a sufficient quantity of protective 4 3 2 1 0 x 2 =
equipment and expendables provided? SF3.3 Are instructions provided for the use 4 3 2 1 0 x _j! , = of protective equipment and expendables? 10 SF3.4 Are operators trained in the proper 4 3 2 1 0 x ~lI~ = use of protective equipment and expendables? SF3.5 Are fire and rescue equipment 4 3 2 1 0x _2_, = periodically checked? SF3.6 Are instructions provided for the use of 4 3 2 1 0. x 2 = fire and rescue equipment?
l l m SF3.7 Are operators trained in the 4 3 2 1 0 x 3 =
- ~ ~ ~ l proper use of fire and rescue j equipment?
SF3.8 Is radiation r.onitoring equipment 4 3 2 1 0, x 2 = periodically checked? SF3.9 Are instructions provided for 4 3 2 1 0 x 2 = the use of radiation monitoring equipment? SF3.10 Are operators trained in the 4 3 2 1 0 x 3 = proper use of radiation monitoring
-equipment?
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9 SG MAINTENANCE AND SURVEILLANCE SG1 h Are maintenance tags securely affixed 4 3 2 1 0 x _2 =
~ to panel components?
SC2 Spare Parts Are inventories kept for operational spare parts and expendables? 4 3 2 1 0 x 1 = 9 O i
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r L.. r :- ATTACHMENT D I. l.t ~ - - BWROG HUMAN FACTORS DESIGN REVIEW OF THE PERRY C0hTROL ROOM I i
SUMMARY
REPORT' t t L j l I< v C
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l l ATIACHMENT D BWR OWNERS GROUP CONTROL ROOM IMPROVEMENTS COMMITTEE BUFJLN FACTORS DESIGN REVIEW OF THE PERRY CONTROL ROOM
SUMMARY
REPORT Prepared By- /d m M C jp, Date / /t f /g t. Kenneth C. Ross Gen ral Electric C any Date I ?U
- epp.Seminara an Factors Consult t Reviewed By '
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.Date W 2-fE_.
G. f. Mullee General Electric Company-
. Approved By.- _p,v [. M Date //27 82, Byr6n Thibodeaux, Survey Tsam Representative /
Gulf States-Utilities
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IMPORTANT NOTICE REGARDING CONTENTS OF THIS REPORT
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. L/ Please Read Carefully This report contains information regarding the Control Room Survey performed under the direction of the BWR Owners' Group with the assistance of General Electric Company. The only undertakings of General Electric Company respect-ing information in this document are contained in the contract between Cleveland Electric Illuminating Company and General Electric Company (Supplemental Agree-ment Number 27, Work Authorization Number 26), and nothing contained in this document shall be cons trued as changing the contract. The use of this information by anyone other than Cleveland Electric Illuminating Company or for any purpose other than that for which it is intended, is not authorized. With respect to any unauthorired use, neither General Electric Company nor the BWR Owners' Group make any representation or warranty, and assume no liability as to the completeness, ' accuracy, or usefulness of the information contained in this documen t.
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CONTENTS
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1.0 EXECUTIVE
SUMMARY
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2.0 INTRODUCTION
2-1 3.0 GENERAL FINDINGS 3-1 3.1 CONTROL PANEL LAYOUT AND DESIGN 3-1 3.1.1 Anthropometric's 3-1 3.1.2 control / Display Grouping 3-2 3.1.3 Color coding 3-3 3.1.4 Labels 3-3 3.1.5 Control Room Layout 3-5 3.1.6 Remote Shutdown Panel 3-5 3.2 INSTRUMENTATION AND HARDWARE 3-6 3.2.1 Indicators 3-6 3.2.2 Recorders 3-7 3.2.3 Indicating Lights 3-7 3.2.4 Switches 3-7 3.3 ANNUNCIATORS 3-8 3.4 COMPUTERS 3-10 3.5 PROCEDURES 3-11 3.6 CONTROL ROOM ENVIRONMENT 3-13 3.6.1 Normal Lighting 3-14 i /N 3.6.2 Emergency Lighting 3-14
$..\ l 3.6.3 Noise, Alar =s, Coccunications 3-14 3.6.4 Protective Equipment 3-15 3.6.51-Storage Space 3-15 3.6.6 Heating and Ventilation 3-15 3.6.7 Sanitary Facilities 3-15 4.0 DETAILED FINDINGS 4-1 4.1 PANEL LAYOUT AND DESIGN 4-1 4.1.1 Anthropometrics and Control Room Arrangement 4-1 4.1.2 Demarcation Lines and Mimics 4-1 4.1.3 Control / Display Grouping 4-4 4.1.4 Color Usage 4-6
-4.1.5 Labels 4 -7 4.2 INSTRUMENTATION AND RARDWARE 4-11
- 4. 2. l' Controllers 4-11 4.2.2 Indicators 4-12 4.2.3 Recorders 4-16 4.2.4 Indicating Lights 4-17 4.2.5 Switches 4-18
.4.3-' ANNUNCIATORS 4-19 4.4 PROCESS COMPUTER 4-24 4.5 PROCEDURES 4-25 4.5.1 Procedure Availability and Accessibility 4-25 4.5.2 Format and content 4-25 r- 4.6 CONTROL ROOM ENVIRONMENT 4-26 (3
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I, c, CONTENTS (Continued)
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Py 5.0 EMERGENCY PROCEDURE TASK ANALYSIS 5-1 6.0 OPERATOR INTERVIEW
SUMMARY
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APPENDICES A. CHECKLIST ITEMS FOR LATER REVIEW A-1 s B. OPERATOR INTERVIEW COMMENTS B-1 l l -C. PHOTOGRAPHS C-1 TABLES I. SURVEY TEAM PARTICIPANTS 2-3 II. CONTROL PANELS REVIEWED 2-4 lO i i l l l i O l
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l l 1.0 EXECUTIVE
SUMMARY
40 in rasponse to recently formulated regulatory requirements for design reviews cf nuclear power plant control rooms (NUREG-0660, NUREG-0700), Cleveland Electric Illuminating Company has undertaken a preliminary human factors cvaluation of the Perry control panels. This one week review was performed by operations and engineering personnel from three utilities, two human factors consultants, and a representative from General Electric Company. General con- ' clusions of the survey team are as follows: FAVORABLE ASPECTS OF CONTROL ROOM DESIGN
- 1. Panels operated from a standing position generally conform to anthropome tric guidelines.
- 2. Panel inserts define system operating areas.
- 3. Panel elements are generally functionally grouped within inserts.
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- 4. Extensive use has' been made of color-coded mimic arrangements to organize system layouts.
- 5. High contrast, easily read labels are provided. Summary labels are used to identify major system operating areas.
'6. Escutcheons are used to associate labels with related switches and indicating lights.
- 7. Color _ coding has been consistently applied to indicating lights on the primary consoles.
- 8. , Visibility of control surf aces within the primary control area is fairly good.
- 9. Controllers and switches are generally withia easy reach.
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fr- 10. Switches are usually actuated in the direction expected by population
.i sterotypes.
II. Guard rails are used to prevent accidental disturbance of control settings.
- 12. Controls are well spaced, minimizing opportunities for disturbing adjacent controls.
- 13. Annunciators are generally grouped by system within panels and are placed above related controls and displays.
14.- The computer keyboard and CRT displays are integrated into the center console. i
- 15. The normal illumination system meets recommended light levels in both primary and backpanel areas.
- 16. The high ceiling illumination in the control room tends to minimize glare and reflections on display faces.
- 17. A highly professional appearance has been created in the design of consoles and room decor.
GENERAL RECOMMENDATIONS FOR ENHANCEMENT I Panal Layout and Design
- 1. Some backpanels have controls and displays mounted above or below optimum heights. -These should be reviewed to determine which, by virtue of importance or frequency of use, might benefit from relocation.
- 2. The dimensions of panel 680 are not optimized for a seated operator.
Careful attention should be given to this panel to ensure that displays, (- labels, and CRT's are readable from a normal operating position. Dema r-
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cation techniques may be.useful to highlight important indications. 1-2
- 3. Operator inputs should be obtained in the simic design process.
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- sO -- - --- .4." Functional groupings of controls and displays on vertical segments of the consoles could be made more explicit through use of demarcation lines and sunsnary labels.
- 5. Some backpanels and the remote shutdown panel would benefit from use of mimics or functional demarcation . techniques.
- 6. A consistent color code should be iuplemented for pushbutton switches.-
- 7. Some labels could be worded more succinctly or accurately.
- 8. The seismic support column between panels 870 and 601 can present a visual obstruction from certain locations in the control room. This concern should be kept in mind when operating stations are selected.
No other items should be attached to these columns, so that the visual obstruction is minimized.
- 9. Annunciator legends on panel 680 are very small and difficult to read from a nor=al operating position.
- 10. Hierarchical labeling should be instituted.
Instrumentation and Hardware
- 1. Control room quantitative displays should be reviewed to determine which would benefit from the additions of markings or color coding to indicate normal, abnormal, and marginal ranges.
- 2. Non-standard, difficult to interpret scales should be avoided where possible.
- 3. Use of larger indicators should be considered for some parameters on panel 680.
b) 4. Units should be specified on all indicator and recorder scales. t 1-3
___ ~ ~ . . -- . p 5. Alarm points should be designated on recorder scales.
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Increased utilization'of poi'n't sielect 'cai> ability should Te 'ediisiderid
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6. for multi point recorders.
- 7. Lany test capability should be provided for indicating lights.
- 8. Shape coding of switch handles should be considered.
- 9. Dnergency switches should be clearly differentiated from other switches.
- 10. Emergency switches should be protected against the possibility of in-advertent operation.
Anrunciators
- 1. Related alarms should be consistently arranged within system groupings.
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. () 2. Larger lettering should be used on panel 680 annunciator windows.
- 3. The usability of the annunciator system could be improved by prior-itizing alarms, segregating informational and advisory displays, abbreviating wordy legends and providing an alpha-numeric code for window identification.
- 4. A first-out feature should be provided.
- 5. Providing separate acknowledge and reset buttons should be considered.
Silence buttons at all panels would be convenient. Computer
- 1. Viewing angles to the CRTs are unfavorable when the operator is seated directly in front of the computer keyboard.
, p 2. The computer is not espable of automatic or manual switchover for ( b' processor failure since there is only one processor. 1-4
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l II gg 3. Color use on CRT formats should be standardized. ib.-) I Procedures ' -
- 1. Procedure laydown space should be provided at the control panels.
- 2. A permanent guideline should be instituted which standardizes all aspects of procedure format and content.
- 3. SOP's should address manual override of ECCS systems in more detail.
- 4. Procedure nomenclature should correspond to that used on panel labels.
Crntrol Room Environment
- 1. Emergency lighting levels are below recommended and should be augmented.
~, 2.- Sharp edges on the primary console guard rails and insert corners
,) should be eliminated.
Procedure Walkthroughs and Task Analysis e Enhancement of the annunciator system may increase the effectiveness of these displays as operator aids. e Certain modifications of display methods and formats could enhance the operability of the control room during transient conditions. e Some information potentially useful to the operator is not available in the main operating area of the control room. e Some modification of instrumentation may be necessary to enable the operator to evaluate the state of the plant in accordance with con-siderations addressed in the guidelines. 1-5
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2.0 INTRODUCTION
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- This report summarises findings of a one week preliminary human factors review cf the Perry control panels using methodology developed by the Control Room Improvements Committee of the BWR Owners' Group (BWROC). A review team com-L prised of operations and engineering personnel from three utilities performed the evaluation, with the assistance of two human factors specialists and a repre-centative from General Electric Company (see Table I). The review was completed on September 25, 1981.
The scope of this preliminary review was defined so as to be commensurate with the current status of the control room. Because Perry is not yet operational, it was not possible to evaluate some sections of the.BWR Owners' Group Control Room Survey checklists. These have been listed in Appendix A and should be reviewed at a later phase in plant construction. Table II lists the panels evaluated by the survey team during the review. 7-Each panel insert was compared to a set of design criteria in checklist form developed from recognized human factors standards. These checklists provided detailed guid= lines for panel layout, panel design, instrumentation, hardware, cnd annunciators. In addition, task analyses of the BWROG Eme.rgency Procedure Guidelines were developed and used to evaluate the adequacy of control room
~ instrumentation.
While the control roem evaluation concentrated primarily on Unit 1, both Units ! cre essentially identical. Therefore, all conclusions discussed in this report should be considered applicable to both units.
- j. Results of the Control Room Survey have been presented in two levels of detail.
General conclusions of the survey team are sunnarized in narrative form in l Section 3.0. Section 4.0 provides a complete list, grouped by subject, of 011 checklists items for which control room modification should be considered. { Af ter each entry, the applicable checklist cross-reference has been placed l in parentheses. k l 2-1 k _ . . . .~~
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- A preliminary prioritization of potential enhancements is also included in the /T ,
U form of Evaluation Products. Rese products have been derived from two numerical - . rating factors, one indicating the degree to which the panel under consideration complies with the checklist criterion, the second representing the relative
- likelihood that non-compliance with that item could cause or contribute to cperator error. De productk of the two factors are then categorized as follows:
9 Modification is recommended 8 - Modification should be strongly considered 6 - Modification should be considered 4 - Modification may be beneficial in some cases Final recommendations for backfits should be determined by the utility in an item-by-item review of these concerns as part of an integrated approach to control room upgrades. This should include an analysis of the safety sig-nificance and frequency of use of the components and systems involved, the con-sequences of operator retraining required by the change, and the engineering Inputs should be obtained from
'O practicalities of instituting the change.
cperations, engineering, training, and human factors specialists. This report identifies areas of control room design for which modifications should be considered, stated as general suggestions with the understanding that corrective action should be considered on a control room vide basis. While specific examples have been provided wherever possible, this document is not designed to serve as an all inclusive list of every piece of hardware for which modification may be beneficial. Nor is it intended to reconsnend specific improvements for the concerns discussed. Topics such as control panel layout should be given very careful review prior to instituting a change as these concerns involve many interrelated factors which sust be considered in parallel. e 2-2
Table I 'C SURVEY TEAM PARTICIPANTS
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Byron Thibodeaux, Gulf States Utilities Robert Sojka, Vermont Yankee Wallace Calvin, Cleveland Electric Illuminating Company , Andy Migas, Cleveland Electric Illuminating Company Kenneth Ross, General Electric Company Joseph L. Seminara, Human Factors Consultant Dr. Paul Nicholson, Human Factors Consultant f( ) O to 2-3
. . . _- .. _ :.2 . . . . . _ _ _ . . .
Table II y The following panels were reviewed by the survey team: IC61-P001 1H13-P807 1H13-P600 1H13-P808 lill3-P601 1H13-P809 1H13-P604 IH13-P810 1H13-P612 1H13-P811 1H13-P614 1H13-P821 1H13-P618 1H13-P823 IH13-P619 1H13-P842 1H13-P621 1H13-P845 1H13-P622 IH13-P865 1H13-P623 1H13-P868 1H13-P625 IH13-P869 IH13-P628 1H13-P870 1H13-P629 1H13-P877 ! 1H13-P631 1H13-P881 1H13-P632 1H13-P882 1H13-P642 IH13-P883 1H13-P654 OH13-P902 IH13-P655 OH13-P904 1H13-P669 OH13-P906 1H13-P670 OH13-P907 1H13-P671 OH13-P969 1H13-P672 OH13-P970 1H13-P680 1H13-P691 1H13-7692 1H13-P693 1H13-P694 1H13-P800 1H13-P803 1H13-P804 10 2-4
3.0 CENERAL FINDINGS O-n
' Q 3.1 CONTROL PANEL LAYOUT AND DESIGN Control panels were evaluated against checklist standards covering anthropometrics, panel arrangements, simic and demarcation lines, control / display grouping, color codes, and labeling systems: Many favorable aspects of panel design were evident, suggesting that considerable attention has already been paid to human factors engi-neering in the design of the Perry control room. Panels generally conform to recommended dimensions, controls and displays are functionally grouped, labels are very explicit, and mimic layouts are used for many systems. However, control room design could be further enhanced in several areas, resulting in a still more effective man-machine interf ace.
3.1.1 Anthropometrics Control panel dimensions were measured and compared to anthropometric guidelines based upon a theoretical operator population extending from a 5th percentile f female to a 95th percentile male. In general, control benchboards were found to NJ closely comply with these guidelines. However, the dimensions of panel 680 do not seem optimized for a seated operator (Photo # 1). The following concerns were noted: o Projecting controls, in combination with the rather shallow slope of the "C" inserts, tend to obscure labels mounted above associated switches l (Photos #2, #3). e CRT's are mounted above the height considered optimum for a seated operator (Photo #4). e When the operator is seated at the keyboard under the lef t-hand CRT, he experiences an unf avorable viewing angle in relation to the center and right-hand CRT's, e The small, two inch high meters used on this panel are difficult to read from a seated position at the center of the console (Photos #5, #6). Q./ l 3-1
_. . . . . . _ . m ~ . . . _ .. . _ . .. _...z. . e Annunciator legends are very small and therefore difficult to read from O a seated operating position. This situation has been recognized and a
,, , program is underway to increase character size (Photos #5, #31).
In view of the potential difficulties associated with operating panel 680 from a fully seated position, an evaluation was made to determine whether this console could be operated from a stool or high chair. W ile this position did afford better visibility of panel labels and CRT's, a lack of knee space became a concern (Photo #7). The main benchboards in the horseshoe, panels 601, 870, and 877, were apparently designed to be operated from a standing position. Several indicators and controls are slightly above recoc: mended limits, but these did not seem to cause any incon-venience for the smallest team member (Photo #8). Non-conformance with anthropometric standards was, in general, more prevalent on the vertical panels, where a number of controls and indicators were found mounted above and below recou: mended heights. Similarly, many elements on the [')a emergency shutdown panel are placed outside of the optimum range, The guardrail on panel 680 (Photo #9) and the edges of the "C" panel inserts (Photo #11) possess rather sharp edges which could potentially cause injury to operators, especially in view of the rather narrow walking space between panels. This threat has apparently been recognized, for one corner of the guardrail on panel 680 has been encased with protective padding (Photo #10). A less obvious hazard occurs when panel 601, 870, and 877 inserts are lifted for maintenance purposes. In this elevated position, the sharp cornus of the insert offer a potential hazard to passersby and to mainti. nance personnel working i below (Photo #12). 3.1.2 Control / Display Grouping Controls and displays are generally divided into system grouping by the panel inserts themselves, each insert being devoted to one or more specific systems. Wen combined with system summary labels, as used on panels 601 and 870, this technique provides effective panel organizations. However, within inserts, some 3-2
consideration should be given to use of demarcation lines to delineate narrowly '~' separated system operating areas and to accentuate important system groupings. Extensive use has been made of mimic arrangements to visually organize controls on the main benchboards and some vertical panels. These are usually well laid out, but operator interview comments indicate that some of the more complicated arrangements may be confusing, RHR being one example. For these cases particu-larly, care should be taken that main system flowpaths are as direct as possible and readily distinguishable from auxiliary and bypass flows. Direction of flow should be clearly indicated and starting and end points identified. It is also recommended that operators be given the opportunity to review preliminary simic layouts prior to finalization and be involved in the design process. Demarcation techniques have currently not been applied to quantitative displays on the "B" panel inserts, where large strings and matrices of indicators are sometimes present (Photo #13). It is recommended that demarcation lines and hierarchical labeling systems be employed to functionally organize these displays. 3.1.3 color Coding O A color code is in effect at Perry, standardizing color usage for mimic lines, indicator lights, and control switches. However, some inconsistencies in applica-tion of this standard were noted, and not all systems have assigned colors. Modi-fications to the standard may be beneficial in some areas to provide greater con-trast of mimic lines against panel backgrounds, and to more clearly differentiate adjacent system layouts. 3.1.4 Labels Tully descriptive, very explicit labels are used throughout the control room. However, these function labels are on occasion almost too explicit and accurate component designations are sometimes obtained at the expense of succinctness (Photo
#14). In fact, the SOPF, controlling procedure formats and content permits abbreviating of panel labels in procedure texts. Notwithstanding possible confusion due to this difference in nomenclature, it would seem that if these A abbreviated designations are descriptive enough for use in procedures, they Q) are also sufficiently descriptive for use on the panels themselves. Panel 3-3
labels could thus be made more succinct with no loss of accuracy. As discussed in section 3.3, an effort is underway to shorten annunciator legends on panel 680, thus permitting larger, more visible lettering. A similar review program might also be beneficial for the panel labels. - Many instances of repetitive labels were noted on the control panels. In a series of related components, the labels may be virtually identical, save for a different component designator (Photo #15). By instituting a hiearchical labeling system, this redundancy can be avoided, resulting in shorter, more concise labels. As a side benefit, this type of labeling system also accentuates functional groupings of panel elements. Initial attempts at hierarchical labeling may be seen on several panels, but the results are not as effective as they might be (Photos #16, #28). Definite size gradations should be used with the larger labels applying to general component stoups. These suunnary labels should be spatially separated from individual component designators so that it is readily apparent that they apply to the entire group. System summary labels have been applied to panels 601, 870, and 877, but to date have not been used on panel 680. These labels help to define panel opera-ting areas and delineate system control groups, thus helping to visually organize panel layouts. Where these system summary labels are used, it appears redundant to repeat the system designation upon each individual component label, as is currently done. System labels thus become a part of the hierarchical labeling system discussed above. Labels on the main control benchboards are written directly on a black escutchien which surrounds the associated control or indicating light. This technique avoids any ambiguity in associating a given label with its corresponding panel elements. Labels on vertical panels are engraved upon plates mounted below the associated components. On lower panel surfaces, these are sometimes difficult to read, as they tend to be obscured by projecting panel elements (Photos #17 - #20). Siellarly, labels on the "C" inserts of panel 680 are obscured by the projecting switch actuators and cannot be read from a seated operating position (Photos
#2, #3).
.O 3-4
3.1.5 Control Room I,ayout f% (A
/._ Visibility of control surfaces of the main benchboards is fairly _ good, although views of panels 870 and 877 from some locations are partially blocked by a support column (Photos #21, #22).
Two functions of potential importance have been relegated to backpanels, namely, radiation monitoring systems and the off gas system. Alarm windows and indicating lights on these panels can be seen over the top of panel 680 if the operator is standing, but not while seated (Photo #23). Traffic patterns within the control room are difficult to evaluate at this time, as the final location of the operator's desk and thewu: shif tor t .supervisors office have not yet been determined. The design of panel 803 has also not been final-ized, but it is known that it will occupy an area in the center at the horseshoe opposite to panel 6B0 (Photo #24). Since this area is a crossover point between the three major consoles, there is a potential for congestion in this area. Depending on the final configuration of this panel and the relative position
'vt o)v of the operator's desk, walking paths and visual access to the control panels may be restricted.
3.1.6 Remote Shutdown Panel Because the Emergency Shutdown Panel is designed to be used under extremely degraded conditions but is relatively unfamiliar to the operators, it is important that its design closely conform to human factors standards. Adequate training is also important to ensure proficiency in its use during an emergency. The following deviations from optimum human factors design criteria were identified (Photo #25): - o Area illumination, provided by a bare flourescent fixture is substandard and uneven. Considerably more light falls across the right side of the panel than the left. Clare and Shadows were observed. o Panel elements are not consistently grouped by system or function. (p RER and RCIC controls are dispersed across the lef t, center, and right
, \"/
sections of the panel. Blowdown valves are not grouped together. 3-5
e controls are not functionally demarcated or simiced to delineate system
,n. ~~q- and subsystem groupings. Panel layouts do not clearly relate to system A_/ operation. .
e The association of transfer switches to related controls is not readily apparent. e Controls and displays are mounted above and below recommended anthropo-metric limits. Parallax and glare were observed on panel indicators (Photo
#26) mounted 80" above the floor (68" maximum recommended).
e Label nomenclature does not correspond to that used on the main control panels. e A good communications system is essential for effective operation of this panel. The operator must rely on auxiliary operators to effect manual con-trol operations, and may also have need to communicate with the technical support center. To date, no such communication system is installed. O 3.2 INSTRUMENTATION Ah*D HARDWARE Control room instrumentation and hardware were evaluated against checklist criteria addressing controllers, indicators, recorders, indicating lights, and switches. Most hardware was found to be in general compliance with recommended standards,.but several specific areas may merit turther attention. 3.2.1 Indicators Meter scales, in some cases, have more than the recommended nine intermediate graduations between numbered subdivisions. In other cases, scale subdivisions are numbered in non-standard progressions which are relatively difficult to ( interpret (Photos #27, #28). To date there has been no attempt at color coding indicators and recorder scales to identify normal and abnormal ranges. Such coding can be a valuable operator (_-) ? 3-6
_ -m- _ -
~ _ _ . _ .
. - ,. . . . ~ , .
A
~
Dm .. . Control room
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- . , , , ; meter.s.,
fit from this e reading of plant parawhich would rapid, qualitativewed to determine aid, permitting ashoul,d be revie i
' very small (approx -
Instrumentation on panel 680, is #5, #6, #29). from normal technique. a pointer (Photos widespread use as indicator, in a fine red line read accurately in some of d uses relatively difficu lt to may be desirable reactor One type mately 2" scales) an are eters, such as of this type styles of indicators Indicators Alternate more important param for the
, viewing distances.ticularly l ced applications, par M period. rticularly those p a plicable to water level and SR some indicators, paare particu were observed on concerns and parallax These Clare control panels. 680 high on the on panel '
meters the miniature recorders control room coded te 3.2.2 Recorders were noted on not color ws
- les are optimum designidentified ve frosted and windo s l dev iations from Sever al are generally lnot ranges.
Some Othere use of chart paper y ,. style gC.* Alarm pointsnormal and abnorma (Photo #30). The proper indicate chart readability to read. from difficult
. detract relatively which are cases.
+
recorder not marked on w by ( to be too lo Indicating Lights was thoughtl control room il 323
~
,;, lights i
'"["*
5 i indicatingreevaluated once finaillumin
- . The intensity This of greenshould assure be that team member. established to 1 conditions have beendistinguishable . indicating clearly in which extinguishedcases, are states j were identified status.
In these no lamp test
.f-
-t Because
* !- . Several instances " normal" system be detected.ascertain if the
..,;j' ., ? might not unable to i used to indicate might be an abnormal condition h operator were indeed defect provided,information, or g,.
', he's been te
- I Nroviding accurate
w --. .~. -- . ... _ .. . . . . . - . . . . 3.2.4 Switches m.
'MU _, . Shape coding of switch handles can be an effective technique for differentia-ting pumps, valves, breakers and other component types. This would enable the operator to rapidly locate a pump control switch in the midst of a complex mimic layout and provide a reference point for tr acing the system flowpath.
While several styles of s' witch handles are in use, no concerted attempt at consistent shape coding was obvious. It is desirable that the operator be able to immediately locate certain potentially important switches such as turbine trips, system isolations, and manual initiations. If these switches are similar in appearance to those inanediately adjacent, rapid identification may be difficult in a time critical situation. It is suggested that such switches be distinctively marked using colored pushbuttons or labels. In some cases this has been done, but the technique is inconsistently applied. 3.3 ANNUNCIATORS
/' With few exceptions, annunicators are generally grouped by system and placed
( - above related controls and displays on the panels. However, some inconsis-tencies in window arrangements were noted within system groupings. For example, on panel 870-7, alarms for trips of steam packing exhausters A and B are arranged vertically (A3 and B3) but the alarms for trips of mechanical vacuum pumps A and B are placed in a horizontal relationship (H2 and H3). Low level alarms for the HPCS fuel storage tank are arranged vertically on panel 601-16 (A3 and B3) but low level alarms for the emergency diesel fuel storage tank are arranged horizontally on panel 877 (A3 and A4). Many diff erent types of alarms may be found within annunciator panels: pu=p trips and system insulators, warnings of abnormal conditions, informational displays describing switch positions and system status, and diagnostic displays actuated by various points in system logic trains. These alarms have currently not been divided by type, but are interspersed among each other. One alternative for enhancing the annunciator system might be to reposition alarm windows within panels into hierarchical arrangements, i.e. place the most significant trips ( Ow and warnings together at the top of the panel. Informational and diagnostic
'- displays would then be segregated in the lower rows of the annunciator panels.
I 3-8
Ris technique facilitates rapid evaluation of system and plant status, as A. the most important information is issnediately provided to the operator. J ~'s .V An. associated enhancement technique involves color coding annunciator windows by type. Red may be adopted to indicate a component trip or system isolation,
' amber to mean a pre-trip warning, blue for system status indications, etc.
This method of coding annunciators provides a visual prioritization of alarms and further accentuates hierarchical groupings. Most annunciator legends describe very explicity the function of the alarm. A design tradeoff is involved here, as exactness has sometimes been obtained at the expense of brevity. In some cases, the precision of the description may actually detract from annunicator readability, as the legends become very wordy., Windov 601-20-A3 for example, " LOGIC FOR LPCS/LPCI FM RHR A DW PRESS HIGH" could alternatively be worded "HI DW PRESS (LPCS/LPCI)." This technique of shortening legends has been employed on panel 680 as part of a program to increase lettering size. The same strategy applied throughout the control room would produce more succinct readable annunciator legends. A number of alarms were identified which are associated with parameters having multiple action levels. Reactor water level, for example has alarms for many different levels; an annunciator reading only " low water level" might signify a scram, an isolation, an emergency system initiation signal, or any of several other trips. Although there are a few exceptions, this ambiguity was generally not observed at Perry. Most such legends clarify the intent of the alarm with additional wording such as 601-20-B3, " LOGIC FOR LPCS/LRCI FM RHR A RPV LEVEL 1.'? However, as discussed above, the utility may wish to consider rewording some of .these legends to achieve more concise descriptions. An alternative wording for the - above example would simply be "RPV LEVEL 1." In any case, it is suggested that the most important part of the legend, "RPV LEVEL 1," should appear on the top line with clarifying statements below. In some cases, adding actual numerical setpoints may also be beneficial. This may be especially appropriate for para-meters with technical specification limits and for those having action levels related to the emergency procedure guidelines. I' . Annunciator windows on panel 680 are very small, making the legends difficult to ( read from a normal viewing position (Photo #5). Ferry apparently recognizes 3-9
this concern, as they have already instituted a program to rectify this situation f (Photo #31). Annunicator legends are abbreviated and shortened wherever possible, Y , then the lettering aise is increased. This technique has resulted in enhanced readability for these windows. However, care should be taken that the abbreviations adopted for these windows are standardized and do not conflict with those used in other areas of the control room. No alpha-numeric location code has been provided for annunciator panels. In order to cross-reference the applicable alarm response procedure, the operator must identify a window by counting down and across the matrix. This could cenceivably increase the chance for error, particularly during conditions of increased stress. Adding reference letters and numbers to the borders of the annunciator inserts would greatly facilitate this process. - The reconnended design for the annunciator response system specifies four separate buttons at each panel - test, acknowledge, silence, and reset. This arrangement is considered optimum in terms of convenience and usability. Alarm silence buttons have only been provided on the '680 panel at Perry. This design may affect operator response paths and increase walking distances during transients. In order to quiet the control room as new alarms are actuated while responding to the situation, the operator must either continually walk back to panel 680 to press the "silen:e" button, or walk directly to the panel having the alarm and press the "sekt.owledge" button. He is unable to silence an alarm from all panels.
" Acknowledge" and " reset" functions have been combined into one butten at Ferry.
This may result in loss of information during transients, as any " cleared" annun-l clators will be reset when subsequent alarms are acknowledged. Alternatively, all information may be retained by using the silence button exclusively until such time when all activated alarms may be reviewed and analyzed. However, this method may require many trips to panel 680 during the transient. 3.4 PROCESS COMPUTER bO The computer keyboard and three associated CRTs are integrated into the center
~
console. As noted earlier, there is some question as to the position that the 3-10
cperator will assume in using the computer. If the operator is seated at the O keyboard, he has straight, head-on visual access to the lef t-most of the three CRTs. .The other two CRTs, however, of fer unf avorable viewing angles. Also, the CRTs are placed rather high for seated operation. Since the operator may have difficulty seeing and reaching other controls and displays while seated ct th'e computer keyboard, there are indications that the computer may be operated from a standing position. ' The computer consists of only a single processor having auto-restart capability within thirty minutes. If heavy dependence is placed on the computer during plant operation, addition of a second processor should be considered. About one dozen CRT display pages were reviewed briefly. Wile great care and innovation has obviously been applied in developing CRT formats, some potential concerns are foreseen. Perry personnel are currently developing their own color coding schemes. If Perry-developed displays and displays frce other ven-dors are integrated into one system at a later time, it may be anticipated that inconsistencies in color usage will become apparent. Furthermore, the Perry displays reveal several internal inconsistencies in the use of specific colors. For example, on one graphic display, the color red is used merely to differentiate core system function from others. Elsewhere, red is reserved for conveying danger, malfunction, or out-of-tolerance limits. Wile the CRT displays reviewed were not yet color adjusted, some of the colors ased for mimics, especially green, appeared very intense. Mimic colors and essociated symbols that are static should be less intense (e.g., dark blue), reserving more intense colors for dynamic information of greatest relevance to the operator. During interviews, operators expressed a desire for more CRT displays using sim-plified P&ID formats. It is recommended that a systematic approach be adopted to incorporate operator inputs in the process of formulating CRT displays. 3.5 PROCEDURES Since few procedures had been prepared at the time of the control room survey, o thorough evaluation of plant procedures could not be performed. However, 3-11
a document titled System Operating Procedure Format (SOPF) is available, serving as a guide to procedure writers. Some preliminary commsents can be provided,
. based upon reviews of this document and .(pitial draf tp of several system operating .
. procedures (SOP's).
The SOFF is, for the most part, clear and complete. Numbering conventions, terminology, cautions, sys' tem lineups, and content are all fairly thoroughly covered. However, a few items may merit further attention. The introduction to the SOPF states that the document is intended to serve as an " informal guide" for procedure writers and that it will have "little, if any, use" af ter all SOP's are written. . If consistency in procedure structure is to be assured, the guidelines provided in the SOPF aust be considered permanent, for-mal requirements, applicable to all procedures currently being prepared and all future revisions. Otherwise, the same conventitns may not be followed by other writers later in the life of the plant. It may be desirable to include some of the information presented in the SOPF it. the f ront .of each procedure or in a general, introductory SOP, particularly ~~ if the 50PF is only a temporary document. Definitions of terms such as "in service," " secured," " jog" and " throttle," value numbering conventions, and electrical designations must be clearly understood by the users of the pro-cedures. This information should be readily available for easy ref erence. Section 3.4 of the 50PF states, "when writing SOP's, approximate numbers should be specified, e.g., increase pressure to approximately 75 PSIG." This practice may not, in all cases, provide suf ficient guldsnce to the operator. Fe r:: 's s ible ranges, upper and lower bounds, and degree of acceptable deviation are not appar-ent from this terminology. gection 3.1 of the 50PF allows paraphrasing of component labels in 50P's. While this practice may result in more readable procedures, it is more desirable
'to always use "as labeled" component designations. In addition, if a paraphrased label is descriptive enough for the SOP, the same simplified wording should suffice for the panel labels themselves, thus resulting in more succince labels.
As illustrated by an example provided in the SOPR, "RCIC PMP FM STRG TANK SUCTION
~
VA1,VE" could be labeled as simply " CST gUCTION VAI.VE" (Photo #14). 3-12
According to the SOFF, panels are referred to by complete name and number the h . first time they appear in a procedure, subsequently by P-number only. If, as .atated in the;SOFF, F-numbers are not unique throughout a- unit, the complete number should be used in all cases, as in some situations a procedure may not be entered at the beginning. The SOFF specifies a conyention for differentiating between units in writing SOP's. Depending upon the circumstances, one S0P may be written for both units with a number symbol (d) replacing the unit prefix in valve numbers, differing valve numbers may be put in brackets, clarifying sentences noting unit differ-ences may be added in brackets, a separate section may be written in the SOP, or completely-separate SOP's may be prepared. In the SOP's reviewed, these methods seemed effective and unambiguous. However, to prevent any possible confusion it is reconsnended that each procedure be carefully reviewed as it is written to assure that unit differences are clearly defined. Separate pro-cedures are probably appropriate for the more complicated systems which have many unit-specific value numbers. On the other hand, emergency procedures are probably best written as applicable to both units whenever possible. No laydown space has been provided at the panels themselves to allow use of procedures while actually operating panel controls. This often means that thr operator must either set the procedure on the panel or hold it in one hand while operating with the other. This arrangement is particularly inconvenient at panel 680. Wo handed operation is often required in a plant startup, during which time the operator m2st continually refer to his rod sequence list (Photo
#32).
3.6 CONTROL ROOM INVIRONMENT An evaluation of control room environmental typically includes a review of normal and emergency illumination, noise levels, heating and air conditioning, the communication system, auditory alarms, protective equipment, personal storage facilities, habitability provisions and housekeeping. At Perry, however, many of the foregoing factors could not be evaluated since the plant is not yet operal tional. Such factors as noise levels and adequacy of auditory alarms cannot be ( assessed until a representative operational environment is experienced. Similarly, 3-13
I I the design of the comanunication system and equipment storage space could not be m evaluated since tr.ese design decisions had not been made at the time of the review. l Despite these limitations, the following general conclusions can be formulated: l 3.6.1 Normal Lighting 1 Normal and backup emergency illumination were measured by means of a WESTON Light l Meter, model 614-60. Typically the light falling on the apron sections of the Primary consoles was greater than the light available on the vertical sections. However, the lighting on all panels either met or exceeded the reconsnended 30-50 foot candle range. A conflict may exist between the ambient lighting environment optimal for view-ing the CRT's imbedded in the center of panel 680 and that for viewing other displays. Use of hoods might be appropriate to provide greater contrast on the CRT's, but such hoods may further complicate viewing angle considerations discussed in Section 3.4. O 3.6.2 Emergency Lighting While normal illumination levels are satisfactory, emergency lighting levels categorically fell below the recommended minimum, ranging from 2 to 12 ft-c. It is recommended that this system be augmented to provide illumination of at least 20 ft-e at panel surfaces. 3.6.3 Noise, Alarms, Communications As noted earlier, noise levels in the control room are not representative during the present construction period. Alarms tested during the review appeared overly intense but such judgements are subjective and not valid until a realistic signal-to-noise ratio may be evaluated. The communications console will be located in a space-limited area in front of panel 680 and will be flanked by panels 870 and 601. The final design of G this console has not yet been determined but it is evident that special care (.,/ 3-14 l
~ - - - - - - _ _ . _ _ ._ ,_ __ __ __ ___f
will be needed to insure that it does not impede the movements of operator C . personnel to and from the three main control panels. . 3.6.4 Protective Equipment Fire extinguishers have bee,n placed in the immediate vicinity of the operator's normal location (attached to the seismic support columns). Provisions for storing protective garments, face masks, air bottles, etc., have not been established at the present time. 3.6.5 storage space Provisions for storing operator personal effects and spares (lamps, chart paper, tapes, tools,.etc.) had not been established and could not be reviewed. Similarly, no storage shelves or cabinets were available for procedures, schematics, manuals, etc. Care should be taken that sufficient storage space is provided for these items without obstructing walking paths. { ) 3.6.6 Beating and ventilation These systems were not fully operational and could not be reviewed. f 3.6.7 Sanitary Facilities Kitchen facilities and restrooms are presently located outside of the control room, at distances of approximately 45 yards and 32 yards respectively. This configuration may prove somewhat inconvenient, and consideration should be given to providing these facilities immediately adjacent to the control room. I-I
- l. .g h-i i
3-15 m
. m .. . .. ._ .
4.0 DETAILED FINDINGS 4.1 PANEL LAYOUT AND DESIGN 4.1.1 'Anthropometrics and Control Room Arrangement Evaluation Produetl
- 1. Panel 680 is four inches deeper than recommended. (A1.1) 4
- 2. The relative positions of Division I and Division II con- 4 trols on panels 622 and 623 differs between units. (A1.2)
- 3. The corners of panel inserts and the edges of the guardrail 2 on panel 680 are somewhat sharp (Photos #9 - #12). (A1.4)
- 4. Operator pathways between panel 680 and other benchboards 6 may be obstructed by the centrally located panel 803 (Photo
#24). (A7.1)
- 5. Views of panels 870-and 877 are parti:11y blocked from some 6 positions in the control room by a centrally located support column (Photos #21, #22). (A7.2)
- 6. The off gas and radiation monitoring panels cannot be seen from the normal operating area (Photo #23). (A7.2) 9 4.1.2 Demarcation Lines and Mimies
- 1. Mimic layouts have been utilized on most inserts of the 9 main benchboards. However, a few opportunities still exist for which this-technique may be appropriate.
i These include the recirculation system on panel 680 (Photo
#33) and the air removal system on panel 870-7, which are currently not nimiced. (A2.2)
)OI-I See.Section 2.0 for explanation of Evaluation Products. 4-1 (
4 I Evaluation Product
- . - - -. 2. ; Controis- and displays on the main benchboards are generally 9 divided into system groupings by the panel inserts themselves.
However, there are occasions in which controls for two systems are present within,one insert. In these cases, use of demarcation lines and system summary labels should be 1 i considered to delineate operating areas and accentuate l system groupings. These techniques might be applied in the following instances: (A2.2). Divide main and auxiliary steam to reheater controls on panel 870-7 (Photo #34). Separate RCIC and LPCS controls on panel 601 (Photo #35). P ~ tinguish relief valve controls from main steam line v alves on panel 601-19 (Photo #36). Delineate standby liquid control system operating areas within panels 601-18 and 601-19. Similarly, use of demarcation lines may be beneficial on some backpanels to divide system groupings and demarcate undiff erentiated matrices of controls. The following examples were identified: -(A2.2) Remote shutdown panel (Photo #25) Panel 970 (Photo #37) ' Panel 655 l Panel 904 (Photo #38) Panel 865 (Photo f40) Panel 845 (Photo (41) Panel 881 (Photo #39) Panel 632 Panel 882 Panel'654 Ak l i 4-2 l
\
Evaluation
) Product l
' ' ' ~' ~
'3 . Within ~ sys tem gr'oupings , additional use 'of ~dema'rc~ation' ' ' '9 i lines may be made to divide subgroups of related com-ponents. The following examples are provided: (A2.3)
Divide A and B recirculation loops on panel 680-4 (Photo #33) Demarcate inserts on the right wing of panel 680 Subdivide the remote shutdown panel (Photo #25) and and panel 845 (Photo f41) Functionally demarcate components on panels 881, 882, 883 and 865 (Photos #39, #40) Subdivide quantitative displays on "B" panel inserts
- 4. While quantitative displays on the "B" inserts of the main 12 benchboards are generally grouped by system above related controls, these arrangements could be accentuated through use of demarcation lines to define system operating areas (Photo #13). (A2.2)
- 5. Graphic techniques used in mimic arrangements generally 4 provide visual distinction between main and auxiliary
'flowpaths. Two exceptions were noted on panel 970, where the fuel pool cooling filter demineralizer and heat exchanger bypasses appear to be main flowpaths. (A2.4)
The blue mimic lines as used on panels 680 and 601 provide 4 6. poor contras t with the dark brown panel background (Photo f42). Similarly, the grey lines on panels 800 and 904 are
- difficult to see against the beige background of these panels. .(
6 (A2.5) 4-3 L
Evaluation () 7.--Dotted white lines are used to represent both the containment Product 4 - -
)
I 1 and feedwater injection lines on panels 601-17 and 601-20 ( (Photo f42). (A2.5) l
- 8. Mimic flowpaths generally appear orderly and easily recog- 6 nizable. However, the RHR system layout on panel 601
\
(Photo f42), the ventilation mimics on panel 904, and the , containment mimic on panel 800 appear somewhat convoluted. (A2.7)
- 9. The mimic on panel 601-19 incorrectly indicates the 6 safety-relief valves in series (Photo #36.) (A2.~)
- 10. Additional use of flow direction arrows may be beneficial 2 in the mimic on panel 904 (Photo #43). (A2.9)
.O Starting and ending points are difficult to identify in the 4
\ g/ 11.
containment and dryvell purge mimics on panel 800 and the nuclear component cooling mimic on panel 970. (A2.10) 4
- 12. A symbol should be devised which more clearly represents the suppression pool than that currently used on panel 601. The present open "U" shape is rather non-descript and is unlabeled (Photo f42). (A2.12) 4.1.3 Control / Display Groupings l
- 1. Controls and displays are generally grouped by system 6-with identical layouts for repetitive groups. Examples of exceptions include: (A3.1)
- a. The arrangements of relief valve indicating lights Viffers
- on panels 601-19, 628, and 631.
w 4-4
Evaluation Product h') ' h -- - b; Equipment drain system components-1rre- interspersed with -- -- -- - :- -- --- --- floor drain system components on panel 881/882.
- c. Standby liquid control system components are, divided between panels 601-18 and 601-19
.d.Drywell pressure and temperature indications are not placed adjacent to each other on panel 601, but are interspersed with containment pressure and temperature.
( e.The RRR controls on panel $01 are separated into lef t-center-right panel segments. The RCIC controls are distributed across center and right panel segments. Relief valves controls are not aligned.
- 2. The ordering of control-display elements was not always 6
() in the recommended left-to-right or top-to-bottom arrangement. Exa=ples are: (A3.2)
- a. Steam lines on panel 601 (18 and 19) are arranged B D A C.
- b. CCW Chillers on panel 904 are arranged A C B from top-to-bottom.
- c. Control-display sequence.s on panel 628 show no correlation to those of related elements on panel 601-19. No obvious numerical sequence was observed on panel 628.
- d. On panel 870-4, condensate inlet valves are arranged in a 2A - 2B - 2C - 1A - IB - IC top-to-bottom sequence.
~ 6
- 3. The association between transfer switches and related controls is not evident on pa'el n 001. (A3.3) f /i g (_,/ 4. The association of selector switches to recorders on
-, panel 883 is not obvious. (A3.3) s 4-5
---a _-- ----_
Evaluation Product J., 1.... Esmt P4ntis contain _yndivided string 3 or matrices of 6 related components. These groupings should be differ-entiated from adjacent controls with demarcation lines, hierarchical labeling, spacing or color coding. The
, following examples' vere noted: (A3.4)
VALVE STM LEAK-OFF switches on panel 865 (Photo #40) Matrix of ARMS on panel 902/906 Meters on panel 970 (Photo #37) Control-display elements on panel 628/631 Control-display elements on panel 881/882 (Photo #39)
- 6. Many backpanels have controls and indicators mounted 9 both above and below recommended heights. (A3.6)
- 7. The' top rows of indicators on panels 601, 870, and 877 6 are above recommended heights. (A3.6)
- 8. Out-of-service switches on panels 601, 870, and 877 are 6 higher than recommended. (A3.6)
- 9. - The' uppermost indicators on panel 680 are higher than 9 recommended. (A3.6)
- 10. The emergency shutdown panel.contains controls and displays 9 l
placed above and below recommended limits. (A3.6) i i [ 4.1.4 Color tisage
- 1. A color code is in effect at Perry, specifying color 6 applications' for simic lines and -indicating lights.
'However, not all systems have assigned colors. (A4.1)
A Blue mimics are used for both the nuclear component cooling
- 2. 6 Q) y and the fuel pool cooling system on panel 970. (A4.2) 4-6 i
I e.
- -~- _. _
Evaluation Product f
~
-- . 3. . Unlabeled white indicating . lights..Are, nsed on panels .-6 , ,
669 and 672 for both LPRM downscale and LPRM bypassed indications. Similarly, red hydrogen purge lights and amber high/ low vacuum lights on panel 845 are not individually labeled (Photos #44, #45). (A4.3) 4.1.5 Labels The following components are missing function labels: 6 1. (AS.1) Four indicators on panel 680-3 (Photo f6) Indicating lights on panels 622 and 623 (Photo f46) Two meters on panel 870-1 Ten switches on panels 881 and 882 Four indicating lights on panel 632 (O One pushbutton on panel 654 Numerous components on panel 845 (Photo f47) One switch on panel 870-5 (Photo f48) Indicators on the right wing of panel 680 (Photos #49, #50) 6
- 2. System labels, seen on panels 601 and 870, are not used on most other panels. (AS.3) i 6
- 3. Panels are generally not identified by both number and function. (A5.4)
(A5.5) 4 f, 4. The following inconsistent abbreviations were noted: SUPPR/SUPR V/VLV SUP/SUPP l-CST /STRC TANK MOTOR FDW PUMP /MTP SUPR POOL /SUPPR POOL /SP l 4-7
Evaluation Product (I "
~ - - - - - ---
6VCE- AIR /S A % ~-- - -- '- ~J --- - INST. AIR /IA CIRC WATER /CIRW , CNTM/CNTMT , DC/ DIESEL CEN MANUAL BLOW /SRV PP/PMP vv/vLv LKD/LD CoND/CNDS OT 3D/orn DR (Door)/DR (Drain) Label syntax is not always consistent. For example, most 4 5. valve labels include a "VLV" designation, but this desig-nation is missing on a panel 970 label reading "NCC TO/ FROM FPCC HEAT EXCHANGERS." (AS.5) s. The terminology used on panel 001 relief valve control switch 6 6. labels does not correspond to that used on panel 601. (A5.5) 6
- 7. Many instances of repetitive labeling were found (Photo #15).
4 Institution of a hierarchical system should be considered to shorten device descriptions and accentuate functional groupings
.of panel components. (AS.7)
- 8. Labels above controls on' the "C" inserts of panel 680 are - 9 obscured by the projecting switches 'and cannot be read from a seated operati.1g position (Photos #2, #3). Labels below components on the lower surfaces of some vertical ,
panels are difficult to see from a normal operating. position. These include panels 600,'632, 655, 800, 823, 842, 845, g 883, 902, 906, 904, 907, and 970 (Photos #17 - #20). (A5.9) ( - t. l. 4-8
Evaluation Product
- . : S. .The following labels. do, mot clearly describe the. fur..: tion. .. : 6.. .. _ ._. _ . . .
of the associated components: (A5.10)
- a. Valve controls on panel 865 are identifird only by number
- b. "RCIC" on panel 632 should read RCIRC
- c. "1P" is incorrectly used twice on panel 870-4, instead #I J "M d" -
- d. The center position marking of switch E31A-513A on panel 632 appears to be part of the function label (Photo #51)
- e. Valve controls on panel 865 are identified by number only.
- f. Containment isolation valve indicating lights on panel 601 p__\
Uj are labeled by number only. 9 Two physically similar, adjacent switches on panels 691 and 694 also have very similar designations - STEAM LINE DRN VLS ISOL LOGIC TEST and MAIN STEAM DRAIN LOGIC TEST (Photo f52). The possibility of confusion could be reduced by more distinctive labels.
- h. The meaning of "PERS AL EL603 OTBD DR LRT SA ISOL VLV" on panel 881/882 is unclear. A more concise label would be more readable.
- i. On panel 601-19, the label for switch B21-F015 currently reads " MAIN STEAM LINE B SAFETY / RELIEF VALVE." The correct legend is "MST LOW POINIS DRN SHUTOFF VALVE".
- j. Reactor water cleanup dump flow indicator G33-R60Z on iq R ./ panel 680-1 is incorrectly labeled " PUMP FLOW."
Evaluation
/~s Product ;( ) - ' " .....:,..... A. The~' condenser' tratuum tri~p' reset'. button on . panel 680 J.: : n r. 'c--
is labeled only "COND VACUUM TRIP."
- 1. " UPSTREAM" and ,"DNSTREAM" designations are reversed i on drain valve indications 2N22-F190A, F230A, F180B, and F210B on pa'nel 870-5.
- m. Labels for valves N25-120A (B) and 125A (B) on panel 870-5 incorrectly imply that scavenging steam is sent to the condensor.
- n. On panel 870-6 identification numbers are reversed on labels for main steam pressure indication upstream of reheater IB and 2A control valves (N11-R146A and R141B) i-l
- o. On panel 870-8, RFPT vacuum trip override switches are 1()' labeled as resets.
I p. RFPT high pressure stop valve before and after seat I drain valve control switches have incorrect numerical designations on panel 870-8 l
- q. Labels for RFFT lube oil test switches and associated indicating lights on panel 870-8 should- specify that a L
pressure test is involved.
- r. "ST SEAL EVAP DRN" on the label for indicator IN22-F270 on panel 870-7 should read 0FF GAS PREHTRS.
- s. The word "f an" should be included on the label for exhaust fan A control switch on panel 870-7 (IN33-C001A).
f t. The label for the low pressure condensor vent valves ()' control switch on panel 870-7 (IN62-FC10) should specify that all three valves (A, B, and C) are actuated. 4-10 L
.. . . = . . - . - - . - - _ . . .. - =_ -- .. - : -. _. . - - - . _ _ . .
Evaluation NfW. Produet I - -
- u. '"RFPT-. A -(5) .ST SEAL LEAK. OEF.. DRIV .VLV".on parel .870 .8 s . : . . ......_ . . . . . . . . .
(IN22-F260A, B) should read RFPT A (B) FIRST STAGE DRN VLV.
- v. The stator water cooling pump reserve cutof f switch on panel 870-9 is labeled only " CUTOUT." Its numerical designation incorrectly implies that it operates stator
~
water cooling pump A. .
- w. Escutcheons are provided for "MST TO 2ND STAGE RHTR B WE DRAIN VLV" control switch on panel 870-5 and for "S/V Sfu V POSIT" indication on panel 680-3, but no associated components are installed (Photos #6, #53).
- 10. Labels are mounted below most indicators, but have been 12 placed above controllers. (AS.11)
Identifying labels on the SRM/IRM drawers on panels 669 6 11. and 672 are not distinctive against the panel background. (AS.13) 4.2 INSTRUMENTATION AND HARDWARE l l 4.2.1 Controllers The following controllers were not easily reached 6 1. l- from a normal operating position: (31.1) l L a RCIC controllers on panel 001 are mounted high. L
.b. Four controllers on panel' 800 are mounted low.
2 i 2. Based on experience 'at the simulator, an operator l (() reported that the RCIC PUMP FLOW controller on panel 601 is too sensitive in the manual mode. (B1.2) l 4-11 L
- , _ _ _ _ . - ~ __ ___. __
Evaluation
'3 t g/~~ Product 3.
V -. _ .a > .. . - 3 .' Contro11-ers:are clearly. marked ~to shew-manual and - 3 == - 40 C-- - . 4-automatic control options. However, on panel 001 the MANUAL / AUTO designations are obscured by the controller lever due to the high placement of the controller. (Bl.3) 4.2.2 Indicators
- 1. Indicator scales are generally not marked or color 12 coded to indicate normal, marginal, and abnormal ranges. (B2.1) 2.- Glare or parallax were observed on the following panels, 9 usually on the uppermost displays: (B2.2) 001 623 803 601 632 804
() 604 619 642 680 870 904 622 800 970
- 3. Process units are not specified on labels for the 4 following indicators and recorders: (B2.3)
IRM/APRM recorders, panel 680 LOOP A/B Flow, panel 680 TOTAL RECIRC FLOW, panel 680 PRESSURE, panel 680 REACTOR LEVEL, panel 680 Bailey recorders on panel 001 Indicators on panel 619 Hydrogen analyzer and glycol pump temperature displays, panel 845 Indicators on pa'nel 811
,m
'- 4-12
'~ -- -- - - ~~
.- ;. .: . ---=-'...: . . . - -.- . .........:. '
Evaluation 7p
' Produet , ...- .. .... ~.c'"The~labe-11'ar 'the 'drywell- prus surrrecorder 'on the einer L~- - -- -- - -- " - - - - - -
gency shutdown panel does not specify whether the pressure is displayed in psig or psia.
- 4. Some indicators and recorders were found for which alter- 6
.nate process units may provide more useful information to the operator: (B2.3)
- a. REATER 1 LEVEL (N26-R042A) on panel 870-4 is incorrectly
, scaled in Ibm /hr.
- b. HEATER 1 PRESSURE and MAIN CONDENSER SHELL PRESSURES on I" panel 870 are scaled in psi vac, whereas in Eg-vac would be more common.
- c. The feedwater check valve indicator on panel 612 is 1(,. ,
inappropriately scaled in amps.
- d. The hotwell level controller on panel 870-2 is . scaled as 0-100, corresponding to dump / makeup (Photo #54).
i The condensate storage tank level indicator on panel e. 870-2 is scaled 0-100%, but procedure references specify level in gallons -(Photo #55). Small_ indicators such as those used on panel 680 are not 6 5. easily read. The control band on the SRM period meters sub-tends a very small visual are when viewed from a normal operating position (Photos f5, #6, #29). (32.4)
- 6. Scales on panel 823/842 are not identified clearly. Units 6 l
are small and often obscured from view. Sometimes the scales
.- are not marked at all. (32.4) 4-13
_.._._ _ .._ _ _ . _ ._ _ _ _ ._.. ~ ..,_ _.__. _ _ , _ . _ - . _ _ _
Evaluation Product
}
-7. - Pointers ' par tially ~ ob^icu .. .-. ~le._ ... . . - . . . .. . . markings or numerals on re sca 4 round indicators located on panel 680 and four indicators on panel 632. (B2.5)
- 8. The direction of thumbwheel motion in automatic controllers 4 is opposite to the resulting motion of the moving scale.
(B2.7)
- 9. On panel 601, RX LEVEL recorders cannot easily be correlated 4 with the REACTOR FUEL ZONE LEVEL indicator since the latter is not labeled or provided units. (B2.8)
~
- 10. On panel 001, references used for water level indications 4
. are at variance from those used in the control room. Also, the SUPPRESSION POOL LEVEL display is not clear since the zero point is not specified. (B2.8) h\J .
- 11. On panel 845, the RECOMBINER A and E DIFF PRESS scales are 4 different thereby rendering comparative reading more difficult. (B2.10)
- 12. Some . indicating devices are not scaled in subdivisions 6 r e.w l,
consistent with the accuracy required by the operator.- l Suppression pool level instruments provide indication to only + 2 ft; a wider range may'be required. On the remote shutdown panel, vider ranges may also be desirable for reactor level and drywell pressure indications. (B2.11)
- 13. A reactor pressure indicator on panel 680 has no scale 6 i
(Photo (6). (B2.11) KD ! 4-14 ,
- - _ _ _ . _ - . , . . _ . - _ . _ _ . . _ _ . _ . _ _ . . _ _ . _ - _ . . - , . _ . - - . _ . _ _ _ - . . . . . _ _ - . - - - . , ~ _ _ _ . - - _ . _ -.
,m.___ ___.__._._._ ,_ _ .
Evaluation Product lh l . . .. . -. . . . . . - - . . . . . . . _ ... . ~ . . . . . . _ . . . .. . .
- 14. The following indicators possess greater than nine inter- 6 mediate graduations between numbered scale divisions (Photos
#27, #28). (B2.12)
Panel-601: C11R100 B/A CRD PUMPS A/B E51-R601 RCIC PUMP DISCH PRESS E51-R602 MST TO RCIC TURBINE PRESS E22-R601 HPCS PUMP DISCHARGE PRESS Panel 001: SUPPR POOL LEVEL Panel 622/623: All meters Panel 632: EQUIPMENT AREA AMBIENT TEMP Panel 642: SUMP LEVEL Panel 669-672: APKM Indicators Panel 823/842: Bailey meters Panel 845: Several discrepant indicators (,) Panel 970: FPCC SURGE TANK LEVEL A NCC PUMP A and B Panel 811: Several discrepant indicators Panel 821: Several discrepant indicators
- 15. Numbered scale divisions that were not in decimal multiples 4 of 1, 2 or 5 were observed on the following panels (Photos #27,
^
#28). (B2.13) 001 680 870 601 800 904 622 821 970 669/672 823/842 1
s n L (g-4-15
l i Evaluation
! Product Recorders - - - - ~ * - - - - L. - - - - - - - - - -- '
" 4.2.3 - - -
- 1. Printed values on recorder charts may be difficult to read 6 on the following panels: (B3.1) l
- a. Panel 601 has mini trend recorders with very small numerals.
- b. On panel 865, a " frosted" cover causes " haziness" in reading the numbers (Photo #30).
l
- c. The lower' recorder scales on panel 883 are not visible from a normal operating position.
- 2. Alarm points are generally not identified os recorder 9 scales. (B3.3)
- 3. The multi-pen recorder on panel 845 does not provide 6
, adequate distinction between markings. (B3.4)
- 4. Some chart recorders are provided with dual speed 6 capability while others are not. The operator is given no indication from the front of the panel to distinguish between single and dual speed capabilities. More wide-spread application of dual speed capability may be desir-able, particularly for those parameters closely monitored during transient conditions and the instruments on the emergency shutdown panel. (B3.5)
- 5. Point select capability is not provided for most multi- 8 point recorders. (B3.6) y 6. Recorders are not generally marked to indicate proper size and type of chart paper. (B3.7) f (D V
!6 h~ 4-16 o
~
Evaluation Product ( ) 4
~
a ..: . _7. Nuclear instrumentation bypas s switches could be . disturbed ... . . when paper is replaced in IRM/APRM recorders (Pheto f56). (33.8) The association of pen color to input parameter is generally 4 8. >. not specified on recorder labels, except for those on panel 680. (33.10) Glare or parallax were observed on recorder faces located 6 9. on panels: (B3.14) 600 680 907 642 800
- 10. - ' Recorder scales are generally not marked to indicate 9 normal and abnormal ranges. (B3.15)
- (tx
-4.2.4 Indicating Lights
- 1. -Green lights on panels 680, 800, and 881/882 were rela- 6 tiveb dim. However, normal operational room illumination conditions have not been established. (B4.1)
- 2. There currently exists no positive means for testing 8 or detecting failed indicating lights. (B4.4)
~
Relief valve position indications on panels 001'and 601 6 3. display only the condition of the actuating solenoid, rather than the actual valve position. (B4.7) 4-17
I Evaluation l 9 . Product g; '- tg
} "- - - -~ -- - ~ - - - - - - - - - - , . . 4.2.5. Switches . . - ' ~ - * '
L __ >' ,
- 1. The direction of switch motions on the following panel 9 601 controls is not in accordance with accepted conven-
[* tions: (B5.1) MAIN STEAM LINE INBD and OUTBD MSIVs close to the right and open to the left. Several switches on panel 001 have escutchons incorrectly 6 2. listing position options as "0FF-1-2" (Photo #57). (35.1) 4 3.- Switch positions were not always clearly marked: (B5.2) , 6 Panel 669 has controls with missing nameplates Panel 800 lacks markings for:
- AEGT A/B CHAN FLTR DELUGE DW Keylock Switch OG BLDG EXIT A/B CHAR FLTR DELUGE CNTMT AND DW EXH A/B FLTR DELUGE AB EXH CHAN FLTR DELUGE .
6
- 4. .Pushbutton switch N22-F3005 on panel 870-8 is incorrectly provided with a rotary switch escutchion (Photo #58). (B5.2) i 6
- 5. Center positions for the following switches are labeled "AUT0", but should be labeled " NORMAL":
IN27-F140, panel 680-3 1N11-F1153, panel 870-6 IN33-F110, panel 870-7
' The center position of switch IN27-C005A on panel 870-8
,h is labeled " NORMAL," but should be " AUTO."
4-18 L. . - -a . - . . . . . _ _ . . _ _ ' * - - - * ' -- -- .- . . _ ,
Evaluation () - -Switches on the following panels-have been placed aboir k- --Product 9 - - ' below recommended heights and are not easily reachable from 1 a normal operating position: (B5.3) 001 632 865 601 669-672 970 604/803/804 800 6
- 7. Operators report that the annunciator pushbutton controls sometimes trap fingernails when depressed. (B5.5) di,ff-Switch handles have not been shape coded to distinguish 8 8.
switch functions (B5.10) ff, 9
- 9. While red pushbuttons are usually provided for manual trip functions, similar distinctive marking is not used to [g s- highlight manual initiation pushbuttons for automatic systems. (B6.1) 4.3 ANNUNCIATOES 6
- 1. While most annunciators are grouped together by system within panel' inserts, a few alarms were identified which could be better arranged: (C1.1) 601-17-E4 and.D5 are separated 601-20-P3 and E4 are separated-All scram signals are not grouped together on panel 680 RHR pump room cooling for alarms are not grouped together on panel 800-R400 containment vacuum relief alarms for A and B trains are separated on panel 800-R405
. Combined gas six system compressor alarms ate separated h' - on panel 800-R405 4-19
w __ -- .....+....- .-.....:-..,...,. .w..._.,.... ,,,_,,....,w. ,. , . _ . . . Evaluation Product (s. p '- - - - - -- - - Windows '904-4t655-A3 sud 33 are invert ed relative- to thr surrounding windows 904-R655-B3 and E3 are separated i I Other alarms ar.e interspersed with low flow alarms on the left side of panel 904-R655 Arrangements for RHR A and B alarms are not identical on panels 601-17 and 601-20 Within system groupings, some inconsistency in arrangements 4 2. of annunciator windows was apparent. Some related windows, such as 601-16-A3 and 33 are arranged vertically. Others, such as 877-A3 and A4 are arranged horizontally. Other examples of this variation in placement may be found on panels 845, 870, 904, and 680. (C1.1) The following annunciators are not located above related 6 3.
.O
(,, , controls and displays: (C1.2) 870-1-H1 870-5-D1 680-7-C9, C10, C11, C12, D9, D11, D12, Ell, E12 680-15-B1
- 4. Annunciator windows have not been grouped by type; i.e., 8 informational and diagnostic alarms are not segregated from trips and warnings. (C1.3)
The following inconsistent abbreviations were found on 4-5. annunciator windows: (C2.1) ST LN (680-1-C3) versus MSL (680-3-A8) CNDR (680-1-A6) versus COND (680-3-A6, A7) ATWB (680-4-E12).
, (y;s ' D/W (680-4-D6, D15) versus DW on other panels RX versus RPV (680-5-CS) 4-20
. . z. . .w. .a-w- .. .... . - .- . . . . . .~..n,_- - .
Evaluation Product CIRW PUMP (870-3-EI) TB (870-3-H2) versus TURBINE BLDG (870-3-HI) Periods are used in abbreviations on windows 870-4-A1, A2 CND STRG TK (870-7-A2) versus CST (601-16-FS)
- 6. Annunciator legends on panel 680 are not easily readable from 12 a normal operating distance due to the small lettering size.
(Photos #5, #31) (C2.3)
- 7. More succinct wording would enhance the readability of the 6 following annunciator legends: (C2.5) 601-21-H1 601-20-A3, B3, C3, DS, E5 601-17-A3, 33, C3, D3 601-17-Bl (delete "B")
601-20-B2 (delete "A") 601-19-A2, B2 680-1-C3, D3, B4 680-4-C1, D1, El, D1, D2, A6, C10, DIO, E10 800-R405-ES, F5 l 870-7-D2 t l 8. Wording for the following legends could more clearly 6 i define .the purpose of the alarm. (C2.5) 601-17-H6 (indicates a particular valve lineup) 601-29-H2 (indicates a particular valve lineup) 601-18-A1, A2, 32, B2 (" identified" means equipment l drain, " unidentified" means floor drain) l 601-21-C6 (unclear whether this is associated with l-RCIC or LPCS) b W 4-21
_- --_-. . . . - . - _ -. . - . - . ~ - - . . - - - . . .- Evaluation Product
]
. . - . .. . 680-4-AS, A14.("needs maintenance" is unclear) - - - - . .- . . _ _ .
Electrical designations on annunciators on panel 870 are somewhat abstruse.
- 9. The following alarms annunciate abnormal conditions for 4 parameters which may have more than one trip, alarm, or action level. For example, "DRWELL PRESS A HIGH" could be an alarm, a scram, an isolation, or a safety system initiation signal. In such cases the annunciator legend should clearly specify the intent of'the alarm. (C2.6) 680-5-B5 870-3-H1
- 601-20-G2, H2, E6 601-17-G1, H1, E2, E5
- 10. The following annunciators may be actuated from multiple 9 inputs (high/ low, etc): (C2.7) 601-16-A2, E5 601-19-G4, H4 601-17-G3, G4 601-20-DS, G4 601-21-66 680-1-A1, A2, A3, A6 680-2-B1, B2, B3 680-3-A9 680-4-A1, D8, E8, A10 680-5-B5 845-A4,- B2, B4, B7, B8, C1, C2, C7, D1, ES, E8 870-3-E3
.870-7-F2, C2 870-9-C2, C3, F1, F2 4- 877-A2 t
l 4-22
w.- ---. :.a ...... . n . ... a ::: ;,.;.;;. :;, wn.,,; ; = Evaluation N)
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Product
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- 11. While some attempt has been made at prioritizing annun- 9 l ciators with color coded windows, application of this technique does not appear to be well defined or consistent 3 on all control paneIs. (C2.8)
- 12. Annunciator panels are not marked with an alpha-numeric 8 location code. (C2.9)
.13. Annunciator audible alarms are not directionalized or 12 (C4) prioritized.
- 14. Silence buttons are only available on panel 680. (C5.1) 9 t
- 15. Separate acknowledge and reset buttons have not been 9 provided. (C5.2, C5.3)
- 16. One set of annunciator response buttons on panel 680 is. of 4 a.different style and configuration from all others (Photos
#59, #60). (C5.5)
J
- 17. A first-out feature has not been provided. (C5.6) 8 l
18 .- The "cause" section of annunciator response procedures is 6 l somewhat long, including sensor identity, setpoint, reset
. point, and possible contributing factors.- This section L should be much more concise. Toward this end, listing sensor identity and setpoint separately may help, and also f make this information easier to locate. (C7.1, C7.2)-
l (.
- 19. There is currently no procedure or window markings to. 12
~
assure'that annunciator legend plates are replaced in their corret locations when removed for maintenance. (C8.1) ( l l
- j. .
i
- 4-23
w-...-_......- n-...-.------.
~ _ ~. . - - - . - .- _ -_ _
Evaluation l
's Product l
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- 20. No administrative procedure is in effect specifying a,. . _, ,
12, , , , j method of identifying out-of-service annunciators. (C8.2) 4.4 PROCESS COMPUTERS While the computer keyboard is appropriately located for a 8 1. seated operator at panel 680, the CRT above the keyboard is placed too high and the other two CRTs offer unfavoraale viewing angles. The operators indicate that the computer will probably be operated from a standing position. (D1.2)
- 2. The computer is capable of displaying selected input infor- 4 mation, however, the C91 has a limited number of inputs (about 800). (D2.1)
The computer is not capable of automatic or manual switch- 4 3. over for processor failure since there is only one processor. ' O.v (D2.7) CRT displays are accessible and easily visible from a 4 4. standing operator position but are too high and at unfavorable viewing angles from a fixed seated position f l in front of the keyboard. (D3.1 and D1.2)
- 5. Color standards for CRT displays are not fully developed 8 l , .
but it appears that locally developed standards will be l in conflict with vendor supplied display formats. (D3.4) 8
- 6. The computer printout is not prioritized. (D4.1)
- 7. The computer output is very difficult to modify and it is 8 not anticipated that output will be periodically reviewed l
and updated. (D4.2) s 4-24
. - . . . - . .:. . ---- :---.-----.-- - _ . . - - . - . . - - - . - . . ~ - -
Evaluation Product
.2. ::::.:u.8. Ribbon replacement on the computer printer is difficult. - .2 .
(D4.7) 4.5 PROCEDURES , 4.5.1 Procedure Availability and Accessibility ,,
- 1. Storage space has not yet been alotted for procedures 12 .J..
and reference materials. When space is designated. -{ . care should be taken that bookshelves do not obstruct _ valking paths in the control room. (E1.5) .
- 2. Laydown space for use of procedures at the panels has 8
( not been provided (see Figure 6-1). This is especially . important for panel 680 (see Figure 6-2). During startup, .. the operator must refer to the startup procedure and the
. rod sequence list. Operators reported that while prac-ticing startups at the simulator they found it necessary to hold the rod sequence list on their knees. (El.7) 4.5.2 For=at and Content
- 1. SOPF guidelines do not specify standardized type size and 6 style for procedures. (E3.1) )
f
- 2. The SOPF does not require the use of as-labeled component 8 designations in procedures. SOP-E51, Reactor Core Isolation Cooling System, requires the operator to verify condensate ,
storage tank level greater than 150,000 gal. However, the level recorder on panel 870 is scaled in 0-100%. (E3.3) ' SOP-C41, Standby Liquid Control System, states that the 6 3. system is to be used only if there has been a loss of re-
}gO activity control. However, the methods by which " loss of reactivity control" may be diagnosed are not discussed. (E4.8)
- 4-25
?
Evaluation Product Q)- 'il
- 4. Valve Idcations are provided only 'on the valve lineup 9 sheets, not in the body of the SOP. SOP-C11 for example, Control Rod Drive System, states, "All controls for this system are located.on the ECCS Benchboard, f H13-P601."
However the procedure calls for oparation of pump discharge valves, which are not in the control room. Care should be taken that the above statement, typical of all SOP's reviewed, is in fact accurate. The procedure should pro-vide locations for valves not in the control room. (E4.12)
- 5. The Precautions and Limitations sections provide technical 6 specification limits only by referring to applicable sec-tions of the technical specifications. Actual numerical limits should be stated. (E4.15)
SOP's do not discuss manual override of ECCS systems during 12 6. 4
% ,/ transients, or specify when the systems may be reset after automatic initiation. (E4.20) 4.6 CONTROL ROOM ENVIRONMENT Glare was observed on the remote shutdown panel, partic- 4 1.
ularly on the uppermost indicator f aces (Photos #25, #26). (F3.2) 4
- 2. The kitchen and toilets are outside the control room and relatively inaccessible. (F6.6)
- 3. Emergency lighting levels are below the recommended 20 .12 footcandles minimum at panel surfaces. (F6.8)
.U 4-26
g 5.0 ENERGENCY FROCEDURE TASK ANALYSIS i A(fJ
# U -The' Baergency- Pr'ocedure Guidelines developed by -the BWR Owners Group will form the foundation upon which Perry's emergency procedures will be developed. Using these guidelines, a task analysis was prepared which identified instrumentation r quired to evaluate plant co,nditions within the framework of the procedural steps.
This instrument list was then compared to the actual control room inven-tcry to verify that the specified parameters are in fact available to the operator. As the first' step in analyzing control room design with respect to the Guidelines, Since exceeding all parameter limits defined as entry conditions were identified. cny one of these limits transfers the operator from normal to emergency procedures, h2 must be immediately aware of the existence of such a condition. This line , of reasoning leads to the conclusion that the presence of any condition requiring
/Gntry into the guidelines should be indicated by actuation of an annunciator, cr otherwise called to the operator's attention. A review of the annunciator panels disclosed that annunciators have been provided for all parameters associated with entry conditions to the guidelines. However, as discussed in Section 3.3, !' certain modifications of the annunciator system could enhance the effectiveness of these displays.
In~several cases, ren ndant annunciators have been provided at multiple locations
-for the same. action level, particularly for low reactor water level and high drywell pressure conditions. These annunciators are used to signify actuation of various points within logic trains and initiation signals for various systems'.
For. instance, six different alarms are provided for high drywell pressure trips, While l l L
-three for level 8 RPV water level, three for level 3 and four for level 2.
t individual system operating areas may be de - repetition of key annunciators at sirable in some instances, it also increases the total number of windows and com-l pounds the amount of information the operator must assimilate during transients. High reactor
'In-any case, the design is not always consistently implemented.
water- level is annunciated for the HPCS system but not for RCIC. Channels [ lA-and B are annunciated for RPV level 2,'but only one annunciator is provided for a low level scram. . Similarly, ~A and B channels are annunciated for sup-for a high reactor pressure scram, l, pression pool level and temperature, but not t.- l L. 5-1
.- a - __.__-._u -_ __. . _ _ . , _ _ _ _ . , . _ . _ , _ _ - - . _ a.
_ =__-________________ . __ Alarms have generally been placed above the related system operating areas. fJ i For instance, the annunciator for a low water level scram is on panel 680, the alarm for.HPCS initiation (levell). is.mn pnaL_6!11 16..and3he 414rJn ..for. . . , , , _ . _ RPV level 2 containment isolation is on panel 601-19. This practice provides indication necessary for each system, but increases the difficulty of mentally integrating all indications to evaluate the condition of the plant. Thus, to determine the status of reactor water level, the operator must look in several different locations. Most annunciators are very explicit in describing the nature of their inputs, but often this has resulted in very lengthy, eVen redundant legends. For in-stance, vindov 680-5-C5, "RPS LOGIC RX LEVEL HIGH RPV LEVEL 8" could be shortened to RPV LEVEL 8 (SCRAM) without sacrificing accuracy. Windov 601-20-B3, " LOGIC FOR LPCS/CPC1 FM RHR A RPV LEVEL 1" could be abbreviated to RPV LEVEL 1 (LPCS/ LPCI) and still supply the same information. The Emergency Procedure Guidelines written by the BWR Owners Group may be con-sidered in one respect as a series of action levels associated with various
/ 'N V. plant parameter, guiding the opera. tor through increasingly degraded conditions.
Displays of these critical parameters must be imediately available in the control room and easily readable, with corresponding limits readily discer-nible. Task analyses and walkthroughs of the Guidelines disclosed the following concerns:
- 1. e If reactor water level has dropped below the top of the fuel, the operator is left with only one water level indicator on scale, which may not be calibrated for the existing conditions.
- 2. e Dryvell and containment pressure instruments are calibrated in psia, whereas trips and alarm points are specified in psig.
- 3. e No direct indication of safety-relief valve position is provided.
- 4. o Suppression pool water level is referenced to normal, but technical specification limits are referenced to the bottom of the suppression
*h pool.
5-2 l
- 5. e No discharge pressure indication is available for LPCS or RHR pumps.
;. r ...a . S . . ; n . A. given.. parameter _ covered- by_ the-r:nidalines;may potsess..several..Acj:imL-levels. Suppression pool water level, for example, has at least eight limits of concern to the operator. Limits or action levels of immediate concern to the operator should be marked in some f ashion on the indicator or recorder. This may include such points as the top of active fuel for reactor water level, normal operating limits and vacuum breaker elevation for suppression pool ' level, and low pressure injection system shutoff head for reactor pressure.
The control room arrangement and the method of organizing controls and displays within panels can directly impact operator efficiency during transient response. Frequently required trips to backpanels detract from the operability of the control room and may affect shift manning levels, whereas conveniently located instruments promote rapid evaluation of plant status. Logically arranged, well thought-out panel layouts enable the operator to locate correct controls and indicators and minimize the change of error. Several positive aspects '! of panel layouts were noted by the survey team in these areas:
- 7. e System operating areas are generally separated by panel inserts
'8. e Controls are generally functionally grouped within panel inserts
- 9. e Extensive use has been made of color coded mimics to organize system arrangements Several other areas were identified in which modifications may be beneficial:
e No reactor pressure indication is available immediately adjacent to safety relief valve controls. 7 ($ e No wide range reactor pressure recorder is availabid on panel 650. e No indication of reactor temperature is available in the main control kt area, i 1 5-3 ) l 1 I
1 l l r
- 10. e The suppression pool level recorder has not been mounted in the main
) control area.
- 11. e CST level is not available in the HPCS or RCIC operating areas.
- 12. e No level indication is available in the HPCS operating area
- 13. e Emergency diesel controls and indications are located on panel 877, but controls and indications for the remainder of .the electrical systems are located at the opposite end of the control room on panels 680 and 870.
Key controls and indicators indentified in the task analyses were compared against pertinent checklist criteria, item by item. This review disclosed the following points:
- 14. e . Wording of component labels is generally very wordy and repetitious.
() 15. e Status lights for containment isolation values are labeled by nu=ber only. t
- 16. e -The full core display contains a large matrix of multi-colored lights.
When under stress, it is conceivable that the operator might miss one - or two non-illuminated red bottom lights. i
- 17. e Verifying correct operation of emergency system status could be facil-3- itated if major flowpaths were made more distinctive.
- 18. e Locating important indications could be facilitated by providing visual
' identification cues, particularly in areas of high -instrument density i .(See Photo #5). . -
3 [ ^19. e Different zero references are used for reactor water level instruments.
; This may complicate comparing readings from multiple indications.
3 5 [J 6 5-4
- 20. e Water level indication on panel 680 is available only on recorders
- b_ and very small indicators in an area of high instrument density. This
- --- --impedes -visual loc ation-and-securate-nadig of this -parametees ----- -
- 21. e The wide . range / narrow range level recorder on panel 680 is missing its label. Another level instrument on 680 is unlabeled; its purpose is unclear.
- 22. e The wide range level recorder on panel 680 has been supplied with an incorrect scale.
- 23. e The left hand wing of panel 680 has a very high density of instrumentation (Photos #5, #6). In the midst of these inserts are some of the operator's most important indications - water level and reactor pressure. These use either very small indicators which are difficult to read from normal operating distances , or are en recorders, which are more appropriately used for trend indication. Larger, more clearly labeled indications would be much easier to locate and use when evaluating plant conditions
( during major transients. Because the Emergency Procedure Guidelines represent a new concept in methods of transient response, certain aspects of plant design will require careful
. consideration when the lp ant specific procedures are written. The following concerns related to the Guidelines were noted:
- 24. e Certain steps within the guidelines address limits which may require instrument ranges in excess of those currently used. Because the actual limits are based on calculations yet to be performed, this consideration could not be actually evaluated at the time of the survey. However, it is probable that expanded ranges for suppression pool level will
'be necessarf.- -
~ 25. e No indication of containment water level is available.
s 26. e No indication of suppression chambet pressure has been provided. v) . 5-5
( .-
~ . .. ..- . . . .
- 27. e The guidelines require the use of bulk suppression pool water temperature and average drywell atmosphere temperature. No provision has yet been
.._,,.de' to olit ain" thes e' " aver' age
- t'ispe raTuf es ."
*~
- 28. e The operator must be able to determine drywell temperature adjacent to reference leg vertical runs.
- 29. e Some limits discussed in the guidelines are "two dimensional," i.e. ,
the operator must correlate two different parameters and plot the result-ing operating point on a graph defining the permissible operating regions. In one case he must relate three dif ferent parameters, utilizing two separate graphs. In a time critical situation this severely compounds the operator's workload and requires careful design of both control room layout and procedures. The parameters involved should at least be situated in close proximity to each other with the associated graph provided nearby. However, a more innovative approach may prove more satisf actory, perhaps involving two dimensional CRT plots or X-Y re-corders. This area of the guidelines must be given extremely close I 1., attention as actual plant specific procedures are prepared. Limits involving correlation of multiple parameters include suppression pool heat capacity, RFV saturation, suppression pool spray, pressure sup-pression, suppression pool load, and heat capacity level limits. Poten-tially of most concern in this respect are limits involving suppression pool temperature and level, as these parameters are located on a back-panel. Specific recommendations for display formatting are contingent upon the final form of the plant specific procedures and the philosophy-utilized in development of emergency response system addressed by NUREG-0696.
- 30. e A given parameter covered by the Guidelines may possess several action levels. Suppression pool water level, for example, has at least eight limits of concern to the operator. Limits or action levels of immediate concern to the operator should be marked in fashion on the indicator-or recorder. They may include such points as the top of active fuel for reactor . water level, normal operating limits and vacuum breaker elevation for suppression pool level, and low pressure injection system shutoff head for reactor pressure.
5-6
- 31. e Entry conditions into the Guidelines may involve action levels not currently addressed by procedures or alarmed in the annunciator system.
- - - - - - - Ar pintme cific -limits-weNefinedi the available annunciators should--- be evaluated to determine if entry conditions are adequately alarmed. Resolutions of the above goncerns will be largely dependent upon the form and content of the final written procedures. In addition, many of these aspects of control room design are intimately related to development of emergency response f acilities, as discussed in NUREG-0696. It is suggested that work in these areas must be a closely coordinated, integrated process if optimum results are to be obtained. O v l j' l ! /T b :' 5-7
i i l i 6.0 OPERATOR INTERVIEW
SUMMARY
------ mrtrptraterr vere-intervieved by the survey team,-ineiuding-five supervis+ng---- ~--- -'
operators, two operations engineers, two associate operations engineers and one reactor engineer. A complete list of all interview cosaments is . attached as Appendix B to this report. In this section, those topics must frequently mentioned during the interviews are listed. Because Perry has no operating his-tory, these comments primarily reflect experience obtained at the simulator.
~
e Six operators thought panel 870 to be rather confusing. Specifically, they found layouts for reheat steam and feedwater vents and drains to be hard to follow. e Four operators found the high density of instrumentation on panel 680 to detract from the usability of that panel. e Six operators complained of trouble reading the small indicators on panel 680.
\.
e The stanchion in the center of the control room was considered a poten-tial obstruction by five operators. k e Five operators desired more space in the control room for procedures, chairs, print laydown areas, etc. L l e Condenser vacuum indicators were thought to be difficult to use by four operators, due to dif f erences in scaling units. I' o Five operators had experienced difficulty in operating the feedwater controller at low flow rates. e Shape coding of switch handles was considered desirable by four oper-ators. o Five of those interviewed requested that an annunciator silence button L, be installed at each panel. 6-1
e Increased use of graphic CRT displays was desired by four operators.
- ~ ~ - - - - e--five- e p'erators expressed-displeasure-with-the-depth-end--eensent-o f--the - ..-- - 1 present training program. i O%e 4
t l t O 6-2
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Y
- e. ,ieme ee .o en amen e sneet em. .am e. ew e + em 4. ee e e emmo aume e y esames one e e er e e we .e o ese esee ._ games .mm eu - e e es Se apman ese m esm*
e e APPENDIX A CHECKLIST ITEMS FOR LATER REVIEW O LJ e f n/
- l A-1 '
Because Perry was still under construction at the time of the review, a complete evaluation of the control room could not be performed. Some items cannot be (
... :_ .. *Islu,at,ed _u,nt.i_1,. a realistic conir.ol room .anuironnent it obeeryable ,-ethers ----- - --
must avait development of plant administrative procedures and definition of operating practices. A complete list of all of these items has been provided j below. While task analyses of the Emergency Procedure Guidelines were developed and compared to control room design, additional work should be performed at a later state in plant construction, concurrent with development of plant specific procedures. A complete analysis requires knowledge of all panels and should involve operating personnel. The following items (listed by checklist number) could not be evaluated at the time of the survey: Panel Layout .ind Design A2.6 Are lives of demarcation, mimics or other graphic displays permanent and
'} maintained?
A6.1 Are temporary changes minimized? A6.2 Are temporary changes controlled in application? A6.3 Are temporary modifications consistent and controlled in nomenclature, font and color? A6.4 Are temporary changes accurate with respect to use or design intent? A6.5 Are temporary changes incorporated into procedures? A6.6 Are temporary changes applied to not obscure adjacent or background information or colors? A6.7 Are temporary modifications reviewed periodically and made permanent
. .fs)
~
or removed? A-2
Instrumentation and Hardware O' BEA6--Ace indi< sting devices-maintained _. calibrated. and:.ausvaillance tested . . _ . , . . on a regular basis? 33.12 Are chart recorders, marked periodically (at least once per shift) and when chart speed is changed with date, time and initials to aid in data recovery? B3.13 Has an administrative procedure been established for recorder chart marking and used chart / record retention? B7.4 'Are keys for key-lock switches administrative 1y contro116.d? B7.5 Where key-lock switches are used do procedures provide specific instructions for use? B7.6 Where key-lock switches are used is switch action smooth and positive
'O V without use of excessive force?
Computers D1.3 Are the computer console and output devices arranged for visual distinction and use of dials, buttons, and switches? D2.4 Is the computer capable of receiving all inputs and performing programmed l functions without becoming overloaded? D3.2 Are CRT displays comprehensible with a minimum of visual search? D3.3 Are CRT displays of adequate brightness for lig,hting conditions or-equipped with conveniently located focus, brightness, and/or contrast controls?
'D3.5 Are CRT displays color coded so that loss of a primary color gun does not result in loss of a numerical value or scale.
l A-3
- - . . . . .c-------,..----------. . - - - - - -
D3.6 Are CRT displays consistent with checklist standards for procedural format (See E3)? D3.7 Are CRT displays identified by system or program? D3.8 Are CRT displays provided with an access mode for display selection (either display menu or sectoring mode)? D4.3 Is the capacity of the typer/ printer sufficient? D4.8 For the computer typer/ printer are printouts easily readable (spacing, headings , fonnats , prints , etc. )? Control Room Environment Host aspects of the control room environment could not be reviewed at the time of the survey. This section should be re-evaluated when a representative en-vironment exists. J U 9 e i
<O ,I -
A-4 (~ _ -- -- --- -
l t I r I I I-L * ' Y## 4 WP eeep. ,, '* & g
*O # -N46 gg g, 9
APPENDIX B OPERATOR INTERVIEW COMMENTS O 9 e e B-1 A
OPERATOR INTERVIEW COMMENTS 00
, V' .
The following is a complete list .of all . opera. tor. comments (see Section 6.0 for _ a summary of these concerns). While responses have been abbreviated where pos-sible, and as such are not verbatim, the intent of the reply has been adhered to as closely as possible. _Refer to actual comment sheets for detailed responses. No attempt has been made in this section to judge the validity of the operators' criticisms or to make any suggestions for improvement. All comments are repeated
'here as a means of transmitting operator concerns to plant management for further review and should not necessarily be interpreted as recommendations of the survey team.
Control Room Layout The stanchion in the center of the control room obstructs visual paths and hinders movement.
.. A
) The printer table blocks walking paths.
The center of the horseshoe is crowded. There is no room for chairs, bookshelves, etc. Chairs will have to have coasters. Laydown space is needed at the panels for logs and procedures. Personnel walking through the control room on routine business will be distracting to the operator; it may be desirable to locate the shif t supervisor's office out-side the control room. Convenient restroom and kitchen facilities should be provided. The off gas panel cannot be seen form the main control area. u.- Control rod drive system parameters cannot be monitored while pulling rods. B-2
. .. n. - .. -.~----------------n-. . . - - - - - - - . - ~ - ~ ~ - - - - - - - - - - - --
L t Fanel Design
- -- ---Panel 870 is- confusing (specifica11yi e h'est steam, heaEer vent and: drain layouts) l f
( The left side of panel 680 is very crowded with instrumentation; labels are small and it is difficult ,to locate desired indications. h L The RHR system layout is involved and somewhat confusing; it is difficult to distinguish the three loops. Mimics should be laid out better. Mimics should show connections to other systems. The association of control valve to related controller is not always apparent. All feedwater pump controls should be in the same place. IRM recorder labels are reversed. Nuclear instrumentation bypass joysticks could be better arranged. The control rod drive system mimic is not accurate. HPCS diesel controls are too close to controls for other systems. The TBCC system controls are not effectively grouped. Recirculation system controllers should be mimiced. Feedwater controllers should be mimiced. The main steam system layout is confusing; it 'is difficult to distinguish isolation valves from drain valves. A consistent color code is needed. b .
- B-3
=- -
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - - - _ _ _ _ _ _- - - _ - - J
,-._;------------------7; , _ , , , , ,_
i Control Room Instrumentation and Hardware >- - -- 1l entaartnacuum indications -have-beettmled ~in many -diffurent sittr-- --- '- - - - Many recorder labels do not provide the units of measurement.
. The small indicators on panel 680 are difficult to read.
Reactor level and pressure indications are available on panel 680 only on recorders. Level instrumentation is scattered throughout the control room. The RHR recorder should be provided with point select capability. Bailey recorders are difficult to read. Bailey recorders of ten jam. It is difficult to change the paper in 3ailey recorders. Suppression pool level should be referenced to the bottom of the' suppression
' pool rather than normal level.
Reactor water cleanup drain flow should be scaled in ' gallons per minute rather than percent. All steam and condensate flows should be scaled in Ibm /hr. Bypass jack demand and actual position indicators should have identical scales. Fanel switches should be shape coded. The hotwell level controller should be labeled " dump-makeup" rather than "0-100." O 9 Throttle valve switches should be distinctively labeled. 3-4 ________ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ ____ _ . _ _ __ _ _ _ _ . _. J
m-.. -
. . _ .. .._ . . . . _ _ _ . _ _ - - _ . - .w. . . . . -
Pushbuttons should be distinguished from simple indicating lights.
?)
p- ---tigtrt*htitrs -ir recorders ; contrerlitrs und--indicatorr are tliificuit-to-replsee.--- - -- Some switches require too much force to operate. The recirculation system controller is difficult to fine tune. The feedwater system controller is difficult to adjust at low flows. The recirculation system controller sometimes gets stuck in the full open position. Controls and Instrumentation Needed in the Control Room A concise display of isolation demand signals is needed. The relief valve mimic should show the geometric arrangement of the valves in the suppression pool. There is no indication of reactor temperature in the main control area. NCC pump control should be at panel 680. Off gas indication should be available in the main control area. Turbine lube oil sump level should be available in the control room. Several additional instruments may be necessary to operate in accordance with the Emergency Procedure Guidelines. These include: Containment water level ADS bypass capability Low reactor water level main steam isolation bypass capability
- B-5 4 -
_________________________________.____________________________j
; Containment average temperature D'
UI
- g. .--- -- --4emt.ainoent -temperatare -ad}aseat..re-lave 3 .ine tresent =actie.al. pipi.ng..runa_. . . --.
An alarm is needed indicating that the auto transfer switch for house loads is not in auto. . Unnecessary Controls and Instruments l Feedwater heater temperature and pressure indicators, panel 870. Suppression pool cleanup controls.
-EHC transfer pump controls.
? Fuel pool cooling to upper containment pool valves. The meters for feed pump RPM and control valve position are too large. I v Redundant generator power indications, panel 680. Controls Prone to Inadvertent Operation The turbine load limit switch frequently gets bumped. Two valves on panel 870, MST to ST SEAL EVAP SUPPLY VLV and EXST to ist STAGE RHTR B DRAIN VLV have similar MPL numbers, (N33-F010 and N22-F010) which sometimes causes confusion. l l The generator breaker (S-610-PY-TIE) and the sync select switch on panel 680 are similar in appearance and adjacent to one another. Manual scram and manual isolation buttons on panel 680 are similar in appearance and close together. O B-6
(. I Annunciators O
. hO.
x )' f.nenieetore- awe ese f-ul -during-norma 1.4perating -conditionsp but. Lass .so .dur.ing _ ; major transients. Annunciator windows shoald,be more logically grouped. More color coding should be instituted. Color coding is not useful. A first out feature would be useful. Too many alarms actuated during transients simply indicate normal system operation. Silence buttons should be installed at every panel. I~')- A different tone should be used for local panel trouble alar =s. v Panel 877 alarms should be part of the panel 601 annunciator system. Annunciator windows on panel 680 are too small. The RHR high conductivity alarm is usually actuated due to stagnant water. The condenser high level alarm is on until approximately 90~ power is reached. Breaker trip alarms are confusing. The logie defeating " low flow" alarms does not distinguish between pump trip and pump of f conditions. Thus, if a pump trips, the low flow alarm is defeated. Computers () More use should be made of graphic displays. B-7
a - S . 0-
, _ ~ -.c. ,,,
-~~...~~.~~----% .s,
' ~ - - . - - - - - , . "% ....
~ ~ - _
! :j- used.
. rs should be t
High speed line printe v
. should be pro ided.
i
'.~ auto log capabil ty
, ' More expanded.
be mod.
; access
- capability should in the i Computer used, particularly
{. should be Interactive dispisys 601 l d at panel w display. A CRT should be instal e
.- windo available for should be More data points should be provided. T displa-windows a hard copy of CR More obtain able to should be The operator designations.
Procedures led" component - should use "as-labe Procedures
! need of updating.
I are in 1 Drawings i ons Systems ent and Communicat for
, needed i.
I Control Room Environm system is l communication i A better point-to-point radios.
;. be placed on
'll should not needed for handsets.
w hes are Circuit cut-out s itc is needed. A better HVAC system
/ . .
. e 3 . * ,
Lighting is too dim.
/)
Q i.l s .- -
- t. ,. '
~
much light. There is too able to die the lig hts
- f. ,
. . , 1 x;
.; should be
. , operator Thexreactor
~N, ' " - ~ - , - _ , . , -'ms -~
Shift Manning and Turnover if V ' ~ ~ ' ' ~ ~ Shif t turnover ' procedures ihoiill require a p1E't foEr'.' ~ " ~ ~~ "" ~~ ~ '
~
~ ~
Shift should be nine hours to allow for adequate turnover time. Two reactor operators should be assigned to each unit. A total o' three supervisors should be on each shift (for two unit operation). Training A comprehensive training schedule should be set up. The training program should concentrate more heavily on integrated plant response to transients. The training program is not oriented to operator needs. Too much emphasis (/ is placed on NRC requirements. More simulator time should be allotted. i The quality and depth of the training program should be improved. Miscellaneous Some valves fully open once started and cannot be reversed in mid-stroke. The diesels start on a loss of power to Division 3 bus, but then trip on high temperature because the ESW valves shut. A reactor water cleanup system isolation must be reset locally. i s RCIC and HPCS start at level 2, but ESW and ECC do not start until leve: 1. This causes high temperatures in RCIC and HPCS. C
\ ;)
i B-9
p Oudit [" i ff
- e w ,g . g .g,g O
e e e APPENDIX C PHOTOGRAPHS O r
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PHOTO #6 ,
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? When Panel 680 is operated from a higher d di.-j hi .- seating position, control surface visibility -
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PHOTO #8 h4v %~ l i?[ g ' The top row of indicators and the out-of- ,2 s
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I _ PHOT 0S #11, #12 , $ .s- -.
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