ML20114D445

Detailed Control Room Design Review Findings

ML20114D445
Person / Time
Site:	Perry
Issue date:	09/24/1984
From:	GENERAL ELECTRIC CO.
To:
Shared Package
ML20114D418	List: ML20114D425 ML20114D428 ML20114D437 ML20114D445 PY-CEI-NRR-0167, Responds to SER Outstanding Issue 7 Re Control Room Design. Summary Rept of Detailed Control Room Design Review Providing Detailed Discussion of Methodology,Conduct,Results & Conclusions Encl
References
NUDOCS 8501310320
Download: ML20114D445 (167)

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l .(- a !(p.J. i F l ATTACHMENT E DETAILEDCONTROLROOMDESIGNh1EIVEW lr. l FINDINGS t PERRY NUCLEAR POWER PLANT SEPTEMBER 24, 1984 r- { l-l hO l c.. L-l I L 6 I 4 ~ t p: n F '~ GEN ER AL h, ELECTRIC NUCLEAR ENERGY RUSINESS OPERATIONS i'- ENERAL ELECTWC COMPANY

• 175 CURTNER AVENUE e SAN JOSE, CALIFORNIA 95125 i

1

GENERAL $ ELECTRIC nh 1 NUCLEAR ENERGY BUslNEss OPERATIONS ~ GENERAL ELECTRIC COMPANY

• 17s CURTNER AVENUE o SAN JOSE, CAUTORNIA 9s125 September 24,'1984 Mr. W. Colvin Cleveland Electric Illuminating Co.

Perry Nuclear Power Plant P.O. Box 97 ( Perry, Ohio 44081

Dear Wally:

The purpose of this letter is to transmit the findings from the Detailed Control Room Design Review (DCRDR) work performed at the Perry Nuclear Power Plant during June 11 through June 21, 1984. This completes the work identified in General Electric quotation number 229 (November 7,1983) and authorized by Cleveland Electric Illuminating Company work authorization number 80 (January 27,1984). The findings of the human factors review have been documented in attachments A through E to this letter. The findings have been . O). termed " human engineering observations". Many of the observations are not human engineering deficiencies. Assessment of the l significance of each observation is required in order to determine whether the term " deficiency" should be assoc.iated with the observation. All coments made by the human ' factors review team have been included. As a result, some insignificant comments have been included. These coments should be simple to resolve. It was also decided to include in the lists, equipment that was removed for service or not yet installed, even though there may be no human engineering deficiency associated with the piece of equipment. The suitability of the missing equipment could not be determined at the time of the review. It was therefore decided that notation to 'this effect was appropriate in the list of observations. These coments should also be simple to resolve. Finally, many of the human engineering observations are related to the written procedures. Although procedural deficiencies are not normally considered to be control room deficiencies, they have been included in this documentation for information purposes. These coments shall be helpful in Perry's emergency procedure validation program. They should not be considered control room deficiencies. ..) 6

GENER AL $ ELECTRIC Lo -Attachment A is-a list of findings from the DCRDR survey checklists. - The table has been organized in.the order of items on the checklists. Findings from the original survey checklist for panels 895, 902, 904, 906, P001, P002 and ERIS appear first, followed by findings from the supplementary survey checklist for all panels. The table provides the checklist item description and number first. Following the description is a list of all of the associated comments along with the related panel number and evaluation product. L Attachments B, C and D include findings from the task analyses of the plant emergency instructions (PEls), integrated operating instructions (101s) and system operating instructions (SOIs), respectively. The table is organized in the order of the procedure steps. In some cases one coment applies to multiple procedure steps. In those cases, the coment appears only once at its first occurrence in the procedure, with references to all following . procedure steps where the same comment was noted. The tables provide a description of the observation, the procedure and step number where it was observed and the panel number and equipment number to which the coment applies. If the comment is related to a procedural problem, no-panel or equipment number is notec. The notation N/A is .used to indicate that equipment,- infomation or control is not available in the control room. In a few cases, information is missing from the task analysis sheet. In those cases " missing" has. .O been noted in the appropriate column. Note that " missing" does not ./ imply a deficiency in the control room, but an ommission in the data collection process. Attachment E documents the findings from Jose h Seminara's analysis of-the operator interviews and questionnaires. Mr. Seminara has . organized his findings-into a photodocumented report format. Attachment F includes the resumes of the human factors review team personnel provided by General Electric; Joseph L. Seminara, Sharen K. Eckert and myself (James W. Howard). I shall be sending you the completed operator interview foms under separate cover later this week. If you have any questions concerning this work or any other needs please feel free to call me at (408) 925-4301.,It has been a --pleasure working with you, Larry and Barney on this project. I look forward to working with you on future aspects of.the control ~ room design review program. Sincerely o m k]. 'ames W. Howard cc: J.L. Seminara A.E. Rogers m P.P. Stancavage C - R.C. Mitchell J.F. Hanlon (W/0 Attach) A

n. &* es O A17ACHMENT A DETAILED CONTROL ROOM DESIGN REVIEW FINDINGS SURVEY CHECKLIST O O

DETAILED CONTROL ROOM DESIG. JIEW FINDINGS - SURVEY CHECKLIST HUMAN ENGINEERING OBSERVATION PANEL Does control panel design generally meet anthropometric measurement A1.1 standards? o Control height reconsnend 42 min, 60 max 6 904 l actual is 27 min, 68 max Display height recommend 48 min, 68 max actual is 32 min, 68 max When panel co;nponents are pennanently removed, are spaces covered A1.3 to prevent debris or dust from entering panel internals and repainted to avoid visual distinctiveness? i j o 2 slots will open 4 902/906 l Are lines of demarcation, mimics or other graphic displays used A2.3 to separate similar subgroups of components within system groupings? o Not used 6 902/906 Are lines of demarcation, mimics or other graphic displays A2.5 visually distinctive between each other and panel / background? ~ o Grey on beige, not enough contrast 4 904 i Are lines of demarcation, mimics or other graphic displays A2.7 laid-out so that flow paths and arrangements are orderly and easily recognized? o Ok within panel constraints 6 904 l A-1

. y_, ~ n \\/ DETAILED CONTROL ROON DESI VIEW FINDINGS - SURVEY CHECKLIST (.,1, EVALUATION CHECKLIST NUMAN ENGINEERING OBSERVATION PRODUCT PANEL ITEM f Are lines of demarcation, mimics or other graphic displays A2.9 clearly marked with arrows to show direction of " flow"? o Needs more arrows 4 904 Are lines of demarcation, mimics or other graphic displays A2.12 consistent in the application of symbols for pumps, valves and other process elements 7 o Only symbol used is pump symbol for fan 6 904 For controls and displays when strings (6 or more) or matrices A.3.4 (greater than 4x4) of components of similar or common function are installed, are they visually distinguishable by lines-of-demarcation, hierarchical labeling, color contrast, spacing, shape, etc. Temperature read / set are dissimilar enough plus.used one at a time 6 904 o indication of temperature at various plant conditions For controls and displays are they generally located in zone A.3.6 "a" or "b" on the anthropometric diagram (See A1.1) o See A1.1 (out of spec) 9 904 A-2

,n () EETAILED CONTROL ROOM EES*. VIEW FINDINGS - SURVEY CHECKLIST (). EVALUATION CHECKLIST HUMAN ENGINEERING OBSERVATION PRODUCT FANEL ITEM i For color use is selected use of colors consistently applied for 44.2 alarm prioritization, indicating lights, labels, lines-of-demarcation, legend plates, graphic displays, indicating devices, tags, etc. o Mimic lines wrong color, lack contrast with panel background 6 904 Are labels, legend plates and escutcheons used to identify AS.2 operational limits or warnings? o RPV dome Pressure & Water level do not show setpoints 6 C22-P001, C22-P002 o Background colors used on panel meters; except on one ananeter 6 904 Are labels, legend plates and escutcheons consistent in nomenclature, AS.5 use of acronyms, abbreviations, etc. (list on Commenc Form and attach) o Hard to tell, probably 4 904 i Are labels, legend plates and escutcheons consistently positioned AS.11 above or below devices and readily associated with ccrresponding controls and displays? o Above controls, below displays; Ok, but not very happy with this 6 904 I A-3 ':

O OcTa'tto C0 ara 0t a00a Ocsi Ovita riar=s - sUmv CutCxust o. EVALUATION CHECKLIST HIMAN ENGINEERING OBSERVATION PRODUCT PM ITEM # When temporary changes or modifications are made, are they consistent. A6.3 and controlled in nomenclature and color? 3 o Yellow tape 4 904 i I When temporary changes or modifications are made, are they A6.7 i reviewed periodically and made permanent or removed? o Unknown ? 904 j From the operator's primary control area is the path to the control A7.1 panel unobstructed? l l o Yes, but need to walk around 6 904 l From the operator's primary control area are control surfaces visible? A7.2 o Control surfaces not visible 12 902/906 l 1 o Control surfaces not visible 12 C22-P001/ I; C22-P002 i o Yes, but not very distinguishable or readable 6 895 i 4 i A-4 t 1 i

O orTAittocoata0ta00aotsiCiviewriaoiNos-suavercatcxtist-EO. EVALUATION CHECKLIST HUMAN ENGINEERING OBSERVATION PRODUCT PANEL ITEM i From the operator's primary control area are annunciator A7.3 windows visible and identifiable? o Annunciator windows not visible and identifiable 12 902/906 o Annunciator windows not visible and identifiable 12 P001/P002 o Not readily; too far away 6 895 Are controllers that require manual operation easily reached? Bl.1 o Some are a bit high/ low 6 904 1 ) Are indicating devices marked to show norwal or abnormal, safe or unsafe, or expected to unexpected range of operation where applic,able? B2.1 j o Indicating devices not marked 12 902, 906 l 1 o. No on chiller amps, yes on temp. 6 904 1 Are indicating devices free from glare and parallax when stationed B2.2 at the panel? P'lastic cover reflects images 6 C22-P001 o C22-P002 o Except for low lying meters 6 904 ] i j Are indicating devices designed so that indicator direction B2.7 follows control movement? o Indirect relationship (possibly meets fully) 4 904 i A-5 1

( ) DETAILED CONTROL ROOM DESI. VIEW FINDINGS - SURVEY CHECKLIST EVALUATION CHECKLIST HUMAN ENGINEERING OBSERVATION PRODUCT PANEL ITEM i For indicating lights is there is a positive means of diagnosing B4.4 failed indicating lights? o One bulb indicating light 8 902, 906 o No, except when light comes on or by unscrewing & substitution 6 904 or lamp test. For indicating lights is bulb replacement easily and safely performed? B4.5 o Very difficult to replace bulbs 4 C22-P001 C22-P002 For switches is each position clearly marked? B5.2 o 3 switches have no nameplates 6 895 For switches is physical distinction provided between pumps, valves, B5.10 indicating lights, divisional separation, power source, etc. o Symbol used for fan; more symbols would be nice 4 904 For switches are handles or knobs shaped so as to clearly indicate B5.11 position without obstruction of legends or confusion of direction? o Message select knob interferes with position indications 4 895 0 A-6 9

. p h> DETAILED CONTROL ROOM DESI Q VIEW FINDINGS - SURVEY CHECKLIST. h,, .c ,) S,- i y% XX ? EVALUATION CHECtll5T' HUMAN ENGINEERING OBSERVATION PRODUCT ' PANEL-ITEM f' ~ .,e g. c - H.c .s ,~

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~ Are switches forJemergency or aonomal use (such as turbine trip.. 86.1 y scram. rmergency.- trip, etc.) clearly marked? o, Annunciator test / reset could be offset / highlighted 6 904 Are' annunciators grouped within annunciator box by specific systems? C1.1 l o Not grouped by. systems 6 904 \\[ Are annunciators. grouped such that warning 'and diagnostic alams C1.3 l are segregated from informational and advisory displays? ~ 0 Not segregated 6 904 y i _ Is alam. window consistent in nomenclature, use of acronyms, C2.1 l abbreviations, etc. o' Alarm window not consistent use of acronyms, etc. 4 904 l Is alam window in accordance with checklist criteria for changes C2.4 l or modifications (see A6)? I' 6 904 l o Seen wordy 1 i Is alam window provided with an alpha-nuWeric code in addition to C2.9 I legends for prompt response and positive procedure identification? o No Matrix Designation 8 902, 906 o Not sure coding is required in this case 8 904 I A-7

{} - DETAILEDCONTROLROOMDESIhEVIEWFINDINGS-SURVEYCHECKLIST h, i EVALUATION CHECKLIST l HUMAN ENGINEERING OBSERVATION PRODUCT PANEL. ITEM f For alarm response, is silence button provided? C5.1 o No alann silence button (to be added later) 12 902, 906 For alarm response, is acknowledge button provided? C5.2 o No alarm acknowledge button (to be added later) 12 902, 906 For annunciator maintenance if bulb replacement requires legend plate C8.1 removal, is there a method to assure plate replacement in correct location? o No location key on lites. 9 904 Is the computer capable of automatic or manual switchover for processor failure ("failover")? D2.7 o Check ERIS computer specialist ? ERIS For the typer/ printer is a backup available? 04.5 o None evident (requirement not evident) 4 ERIS For the typer/ printer are paper and ribbon easily replaced? D4.7 o Check ERIS computer specialist ? ERIS A-8

DETAILED CONTROL ROOM DES. REVIEW FINDINGS - SURVEY CHECKLIST EVALUATION CRECKLIST NUMAN ENGINEERINC OBSERVATION PRODUCT PANEL ITEM # Are CRT displays color coded so that loss of a primary color gun 13.5 does not result in loss of a numerical.value or scale? Generally true; have a RED, CREEN and BLUE dot in lower right 4 ERIS o corner of each screen to indicate color is available. Could lose a value that uses one of these. Are CRT displays provided with verification that the computer is 33.9 operational and that data is being updated on a periodic basist Check ERIS computer specialist ? ERIS o i i A~9

f }~ k DETAILED CONTROL ROOM DES. G EVIEW PINCINGS - SURVEY CHECKLIST j, EVALUATION CHECKLIST-HUMAN ENGINEERING OBSERVATION PRODUCT PANEL ITEM f d Is sufficient space allowed between the panel and opposing surfaces SA1.2 such that the operator may perform required tasks without hinderance? o Clearances around panel less than recommended 4 805 29" between bookcase and edge guard - check standard? ? 870 i o o Operator has to squat to read lower recorders; this will block 4 883 aisle for other personnel (7" less than recommended 50") o Less than 8' recommended 6 902 o A little tight 4 904 i i o Less than 8 Ft reconenended 6 906/907 i Can't readily tell with temporary furniture; probably ok 4 970 o Slightly less than 50". recommended 4 C22-P001 o Slightly less than 50" recommended 4 C22-P002 o Does the location of the shift supervisor's office permit prompt SA2.1 access to the control room under all conditions? o Shif t supervisor remote and unit supervisor view blocked-need 6 680 mirrors o Shift supervisor outside control room 12 Ceneric (877) o Location not yet determined ? Generic 1 A-10 t I

hflEWFINDIES-SURVEYCHECKLIST^ h DETAILED CONTROL ROOM DESIf EVALUATION CHECKLIST NtmRN ENGINEERING OBSERVATION PRODUCT PM ITEM f i Are operator's desks and chairs comfortable and in good repair? SA2.2. o Should be provided 4 Remote S/D i For a multi-unit plant, are senior operators who supervise or assist SA2.3 j in the operations of more than one unit stationed such that they may connunicate effectively with all operators and view each control board? ? o Senior operators will be able to communciate with. plant operators 4 Generic via communciation systems. They will not be able to view both unit control boards at the same time. 1 i l Are operators provided with sufficient desk and working space for SA2.4 performance of required tasks? i l No desk space at 680 for start-up tasks. P805 has writing sur' ace 2 680/800 f o i directly behind 680 I j o Need cart for procedures laydown 2 845 i i o Assumed 2 904 1 1 o No working surfaces provided at this time. PA available 4 Remote but more elaborate communications provisions will be needed S/D Panel q I! I i j

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._ n r (. L DETAILED CONTROL ROOM DESi IEW FINDINGS - SURVEY CHECKLIST ( _ _/, m/ EVALUATION CHECKLIST HUMAN ENGINEERING OBSERVATION PRODUCT PANEL ITEM i Is the association of feedback indication to related controls 3A3 made readily apparent through labeling, mimics, demarcation lines or position? o P601-16-No Reactor level indication (nearest is on P601-20) 6 601 o P601-16-No demarcation for generator and pump indications 6 601 o P601-20-ECC water mimic is green - however this is fresh water 6 601 o While apron section mimicked, the vertical section not 12 680 differentiated to allow easy association between controls & displays o No feedback from controls: 9 618 E12A-S44B E12A-S70 E12A-S72B i E51A-S44 Unmarked switch E12A-J1 o No feedback from 6 621 RCIC Logic A Power monitor test o No direct feedback from 6 625 i E22A-S24 Unmarked switch o Indicating lights seem very confusing 6 628 A-12

(~]) .DETAILEDCONTROLROOMDES!jllEVIEWFINDINGS-SURVEYCHECKLIST J., m EVALUATION CHECKLIST HUMAN ENGINEERING OBSERVATION PRODUCT PANEL ITEM i o No feedback for 6 629 E12A-S44A E12A-512 E12A-S13 E12A-514 E12A-S72A E12A-515 o No feedback on 6 632 E31A-57A.-58,-510,-S13A -51A,-S2A,-S4A E51-545 (is this associated to leak detection 7) o No feedback for E31-513B,-518.-S28,-54B 6 642 o No feedback for E32A-S4,-516, E31A-513 6 654 o No direct feedback for System A.E,J,N initiation. Inboard system 6 655 out of service. o No feedback for B21H-S19A.-S20A,-521A,-571A; C71A-S6A.-57A 6 680 o No feedback for B21H-5198,-520B,-5218 -571B; C71A-568.-S78) 6 692/693/ (C's on 693, D's on 694) 694 o Some changes needed 6 800 o No mimic or demarcation 12 845 o Undifferentiated displays - not tied to mimics or functionally 9 870 demarcated o S controls not labeled, all other labels are temporary 12 895 A-13

f DETAILED l CONTROL ROOM DESIOrview riaaraas - suaver caccx'rs':6 EVALUATION ' CHECKLIST 4 HUMAN ENGINEEMING OBSERVATION PRODUCT PANEL ITEN # i l 0 S: u s,11ays appear disconnected; others reeded a mimic 6 904 i o The related controls are located on P680-HEI (as designed) and the 12 C22-P002 indications are located on C22-P001/002, which are not visible from P680. j o Indications not integrated..into the mimic; however, very 9 Remote ]. few indications to'be concerned with S/D panel Where abstract symbols are used, are they of standard configuration, SA4.1 distinguishable from other symbols..and consistent in use within and across panels? o Need Hx symbol (water / air) in mimic 6 800 i o Two " arrows" on transmission station mimic are non standard 4 808 t i .and are similar to flow control symbol used elsewhere l o -No symbols. should be some 4 845 l i o Symbols 4 904 o Some abbreviations non standard (HSKBG, R for RUN, INIT'D) 4 C22-P002 l t i Are labels located such that they do not cover or detract from SA4.2 other necessary information? o Point designati9n labels (on Tracor recorders) cover 1/4th of 9 811/600/ the trend information 614 o Calibration stickers cover labels on Bailey cards 9 612 i A-14

EVALUATION CHECKLIST HUMAN EMINEERIM OBSERVATION PRODUCT PANEL ITEM f o Selector point labels cover trends _(E31-R611; E31-R608) 9 632 o N31-R004 & N31 R005 cover and block trending capability 6 823 o N27-R066, N21-R216, N71-R216 - covers half of recorder area 6 842 o Some temporary labels, recorder labels 6 845 o Point labels. cover half of recorder glass (must open to read) 6 865 o Point ID labels cover 1/3 recording space 6 883 o Recorder point ID labels cover portion of glass. Operator must 6 907 open front cover to obtain full use of trend capability Is extraneous information not included (e.g., manufacturer's SA4.3 trademark,patentnotice,etc.)? o Vendor labels on chart recorders, control _lers 2 601/823 o GE label on range selector panel 2 842/680 o Chart recorder - manufacturer label and trademark 2 800/811 o Manufacturer's description 2 807/808/ 809 o Some extra info in lower left corner of some labels 2 845 o All Bailey & GE units have logo 2 846/865 o Rosemont & Bailey 2 868/869 A-15

O at'ato co"'ao' aoo" oes' (Dvib t'"o'"as - soavev c"tc"5' O. EVALUATION CHECKLIST HUMAN ENGINEERING OBSERVATION PRODUCT PANEL ITEM i o All recorders have manufacturers logo & trademark 3 883 o Manufacturer's logos on equipment 2 902/906/ 907 o PANALARM tempmatic (not too intrusive) 2 904 o Peak shock annunciator has manufacturer trademark, partially 2 969 obscured by nameplate For a multi-unit plant, are alarms for shared plant systems duplicated SAS.1 in all control rooms? o Some alarms on one, not on other 12 680 o Alarms only in unit #1 12 904 o Common alarms are on P970 in unit I control room; only seismic, 9 969/970 trouble alarm is duplicated For multi-unit plants, if equipment is shared between control rooms. SAS.2 is there administrative control over use of the equipment? f o No procedure in place 8 generic Is the status of shared equipment displayed in each control room? SAS.3 o Only by annunciator 6 902/906 o -Only unit #1 12 904 A-16

h. DETAILED CONTR0t. ROOM DESK VIEW FINDINGS - SURVEY CHECKLIST. EVALUATION CHECKl.IST ~ MtMAN ENGINEERING OBSERVATION PRODUCT PM ITEM # o Recorders located in unit I control room. No display in 6 907 unit 2 control room o One panel is in unit I control room; status for M25, M23 and P42 9 969/970 common equipment not found in unit 2 control room; unit 2 PE80 does have alarm for seismic monitor of P6% Are indicator scales easily read when stationed at the pane 17 $81.1 o Parallax on lower two recorders 6 842 o Operato. must squat to see lower meters and recorders 6 823 i o Indicator scales are small 6 694 o Frosted glass - hard to read through 6 865/632 Tracor recorders'have frosted glass - cannot read scale 8 600 o o Tracer recorders have frosted glass - cannot read scale 6 614 o Indicator trip units - scales are hard to read 6 618 o Rosemount trip unit scales are small and hard to read-6 693/692/ 680/655/ 625/654 o Bailey trip units.are small and hard to read 6 629 o Mini-scales offer poor readability 12 680 o Four frosted glass recorders impossible to read w/o opening 12 883 A-17 ~

.n DETAILED CONTROL ROOM DESIC VIEW FINDINGS - SURVEY CHECKLIST EVALUATION CHECKLIST HUMM ENGINEERING OBSERVATION PRODUCT PM ITm i o Three meters hard to read lower end of scale from standing 6 904 position because placed too low to ground (M21-R064A & B P47-R291) o Process unit labels small 6 907 o Scales within visible reach. Permanent illumination not yet Remote installed and should be checked later S/D panel Is the use of multiscale and logrithmic scale indicators minimized? S81.2 SRMS have recorder scales 10-I to 10-6 4 680 o o All scales are log MR/HR 8 8 13 o All scales are log CPM 8 804 o 4 Dual scale recorders used 4 823 o Temperature meters have 2 scales - no way to tell which to use 4 868/869 E31-R3718(C) (See also P869) o Exceptions: STATOR CLG WTR IN/0UT CONDUCTIVITY (N43-R037,-R172) 4 870 o Four 3-pen recorders have 3 different scales - 2 temperature 6 883 recorders have 2 different scales o All rad monitors are log 4 902/906 o All log 4 907 Are displays which reflect only a demand signal labeled accordingly? 581.3 o Bailey controllers - demand signal not labeled 12 601 ,o Label controllers 12 680/800 A-18 +

e - O oETAltEnCONTR0tR0aaoEsrcO.viEvriNoiNas-SURvErCNEC=tisT N v.- EVALUATION CHECRLIST HUNRN ENGINEENIM OBSERVATION PR0oUCT PANEL ITEM # l o Controllers 6 845 870 o Controllers should be labeled 12 + o Bailey controller output meters not labeled 12 969 o To be determined ? Remote S/D panel 581.4 Are process units and multipliers specified? o Not process units on E31-R61 6 642 o Not on controllers 12 800/680 No process units specified in % [C11-N601A, C71-N652A, E31-N686A. 9 691 o E31-N686(7)A E31-N668(9)A] { Labeled in 1 (same as panel 691, for 'B's)(694 for o's) 6/9 692/694 o o Marked in % (C11-N601C, 652c) 9 693 o M41-R010, Gen. Temp, 511-R010 transformer temp 12 811 o M31-R003 no process units 6 823 Small process unit lettering on Tracor recorders 6 842 o (noted on all panels) No process units are specified on recorders 12 600 o 6 614 No process units on B21-R643 o o Scales in % - (5 scales) 6 629 A-19

~ ) DETAILEDCONTROLROOMDESIChVIEWFINDINGS-SURVEYCHECKLIST ('"), ~ EVALUATION CHECKLIST HUMAN ENGINEERING OBSERVATION PRODUCT PANEL ITEM i o Scales in % - E22-N656 9 625 o Scales in % - JET pump monitor - B33-R610A-W 9 619 o Place units on controllers, e.g., GPM not noted 12 601 o Five scales are in % 9 618 o Not on controllers 6 845 o Core monitor recorder has no process units 12 864 o Tracor recorders ("F) are small 6 865/883 o Controllers show no units 12 870 Bailey controller not labeled except for "0-100" on drum 12 969 o Bailey controller (RCIC TURB flow control) no units; 6 Remote o chart recorders (3) not labeled S/D Is all recorder information visible through recorder windows (i.e. 582.1 open-door operation not required)? o Tracor recorders have frosted glass - cannot read scale 8 865/600 o Anti-glare window on recorder E12-R601 impedes reading 4 811/601 (Operator opens cover to read) o Fogged Westronics recorder windows 4 800/842 o Labels obscure portion of chart paper 4 823/842 o Labels block veiw; frosted glass makes chart paper fuzzy 8 907 ~ A-20 9

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DETAILED CONTROL ROOM DES! b EVIEW FINDINGS - SURVEY CHECKLIST (J., EVALURTION CHEttLIST NINut ENGtWEERtWG OBSERVATION PRODUCT PNEl. ITEM i Have procedural or design provisions been implemented to prevent 583 interchanging indicating light lenses? o No procedure in place. 8 Generic Where contiguous legend pushbuttons are used, are barriers provided $84.1 to prevent inadvertent actuation of adjacent pushbuttons? o Pushbuttons on countrate meters do not have barriers 12 604 o No barriers - need to code switch lites to differentiate 12 680/870 from indicators o PMG and horsepower reset pushbuttons not separated or protected 9 821 Are key-operated switches used only where appropriate (i.e., to S84.2 prevent unauthorized control actuation)? o Concern that keys will be removed and stored in shift 4 601 supervisor's office (remote from control room). Prefer to leave keys in control room and use the key feature to highlight an important control Do numeric keyboards conform to either the " telephone" style or the 501.2 "calcilator" style arrangement? o Non conformant to telephone standard 4 ERIS is: 7 8 9 should be: 1 2 3 4 Process camp. 4 5 6 4 5 6 1 2 3 7 8 9 0 0 A-21

O atTAitE.ce=raatRai=EsicOviEvrii=iais-suRvETcaEcttisi l}: ~ EVALURTiON DECELIST MpWN M N SBSERVATION PRODUCT PAIEL IrDI f } 501.3 Do function keyboards contain only those keys which are used by)the operators (i.e.. no irrelevant keys-such as used by programmers ? I o All/most alpha numeric keys not used 3 ERIS 3 Process coup. Are function controls clearly labeled to indicate their function? 501.5 l o Reys have numbers but no function indication 4 ERIS o No. Legend sheet loosely placed on PC keyboard (keys unmarked) 4 Process comp. ( .t Is computer use and software access administrative 1y controlled? $02.1 k 7 ERIS o Defer Process coup. l Is the system designed such that data is not lost during printer 502.2 down periods? i o Defer ? ERIS l Process camp. l l Are CRTs free from glare and easily readable from normal viewing 503.1 positions? j o Glare generally under control but same reflections present. Anti-4 ERIS } glare shields rewoved due to dust / dirt & scratches l o Bad reflection from white console table top; (darker color needed) 6 Process comp < r l t A-22 j t

O -ot1Aitto Con 1R0t R00M otSic t itw rinoiNc5 - SURvtv CaECxtiS1 (D.- EVAtUATION CHECKLIST HUMAN ENGINEERING OBSERVATION PRODUCT PANEL ITEM f l' I Are messages which require immediate operator response highlighted to SD3.2 attract the coerator's attention? o ves; colors / blinking bring off-normal points to greater attention 6 Process Comp, on displays being viewed; can't see points on other displays; need higher level " ding" to signify alarm. I Are prompts and error messages used to guide the operator in proper 5D3.3 l system operation? o Only alarm and performance logs. Other plant status on ERIS P&ID's 4 Process comp. E Are abbreviations, acronyms, and synonyms used consistent with those SD3.4 i used elsewhere in the control room? o Need abbreviations list 4 ERIS j, ~ o Can't tell; no standard list but no serious problem in reading 4 Process comp. legends j l' is the system capable of providing a hard copy of any page appearing SD4.3 j on the CRT? o Some but not all 2 Process Comp. I, Are procedures, reference raterials and other documents readable (i.e. SE1 not dirty, torn, dog-eared or otherwise difficult to read)? o Procedures not at this station at present time. Required reference 12 P001 materials to be determined t A-23

O ot1Aittoc01R0tROOnotSie.viturinoiNGS-SuRvercaccxtiS1 r=J'. x_ HUMAN ENGINEERING OBSERVATION O PANEL E is a set of computer operating procedures available in the control SE2 room describing the computer system, procedures necessary to accomplish operator-computer interface functions and congingency actions in the event of a computer failure? No procedures in place in the control room for ERiS or the process 8 Generic o computer Since ERiS will be incorporated into this station, it may be 8 P001 o necessary to incorporate ERiS procedural data SF communciations Section SF - These items could not be evaluated at the ? Generic o time of the survey. To be evaluated later SG,2 Spare Parts - Are inventories kept for operational spare parts and expendables? Spare parts inventory (lamps, light bulbs, etc.) should be 4 P001 o considered since control room supplies will not be available A-24

.t s. O ATTACHMENT B DETAILED CONTROL ROOM DESIGN REVIEW FINDINGS TASK ANALYSIS - PEls.. O l l I 1 '5 O L

e, DETAILED CONTROL ROOM DESIGN REVIEW INGS - TASK ANALYSIS ?- PROCEOURE STEP PANEL Equ!PIENT N ENGIIEERINE OBSERVATION HINSER NUMBER NUMBER NUfGER p o Level 3 is not indicated on the following instruments: PEI-1 2.0.1 b 4 A. Wide range meters / recorders P601 821-R623A P601 821-R6238 l ) 8. Narrow range meters P680-38 C34-R606A P680-38 C34-R6068 P680-38 C34-R606C C. Narrow range recorder P680-38 C34-R604 D. Narrow range recorder P680 C34-R608 j E. Shutdown range level meter P601 821-R605 1 j F. Upset range recorder P601 C34-R608 1, i 4ie 4 o Scale increments on wide range level reccrders are PEI-1 2.0.1 P601 821-R523A H 4 i 2.5" with 5" and 25" highlights. Inconsistent with P601 B21-R6238

i!

l 1,2 or 5 unit standard. 1 i o Reactor pressure meter is very small, hard to read PEI-I 2.0.2 P680-38 C34-R605 1; with fine resolution. 3 o Reactor pressure meter scale is blank PEI-1 2.0.2 P680-38 C34-R605 I I o Level 1 annunciator is mislabeled as " level 2" PEI-1 2.0.3 P601-19A R61r 83 p Je 5 o 2 annunciators for NSIV high radiation is a compli-PEI-1 2.0.3 P680-7A R61 D4 l cation. One annunciator could serve necessary purpose. P680-7A R61 E4 l,. l 8-1 l t

p neva 7t en r*rurTont annat nrcT viFU PTMnTMf*C..TACF AMATYCYC PROCEDURE STEP PANEL EQUI HUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER Annunciator window missing for "MST Turbine Area PEI-1 2.0.3 P601-19A R61. El o R61. F1 Temperature" annunciator R61 C1 R61. H1 Drywell pressure meters in units of psia and PEI-1 2.0.4 P601-20B D23-R046A o D23-R046B procedure specifies psig. PEI-1 2.0.4 P601-208 D23-R046A Dryvell pressure meter A currently missing o Regulatory guide 1.97 not identified on DW PEI-1 2.0.4 P601-20B D23-R046A o D23-R046B pressure meters Pens / indicators missing on DW pressure recorders PEI-I' 2.0.4 P883 D23-R180A o D34-R1808 PEI-1 2.0.5 P680-6D2 C51-R603A Paper in APRM/IRM recorders scaled for APRM o C51-R6035 only (not IRM) C51-R603C C51-R603D Currently a dual scale on IRMs 0-40 scale not PEI-1 2.0.5 P680-6D2 C51-R603A o C51-R6035 used, plan to change in future. C51-R603C C51-R603D B-B-2

O- .ETAitE. A R0oM.Esi. O vie riiWi s - TAs= AaR<vsis 17 PROCE9WE STEP PAIEL ESf!PIENT IW WI ENSIM ERI S W SERVATION NtpWER NISSER IRpWER IUWER i! i: o Ito single annunciator to report scram except for PEI-1 2.0.5 Generic s mode switch annunciator (question C.5 operator to plant interface questions) L 1 o Annunciators are not easily readable - too small. PEI-1 2.0.5 P680-6A R61,85,C5, DS.E5 P680-6A R61.B3 C3, J D3,E3 P680-5A R61,07,C7 t P680-5A R61,06,E7, d E9,E8 o Annunciator currently not as indicated in checklist. PEI-1 2.0.5 P680-5A R61.C4,04 4 (Due to be changed within 6 weeks) o No direct reading of suppression pool temperature. PEI-1, 2.0.6 P883 D23-R090A [ Must be calculated by operator. PEI-1 3.1.9 P883 D23-R0908 o There is no digital indicator for 110*F suppression PEI-1 2.0.6 P601-17A R61,63 d pool temperature (procedure setpoint). Only a 95'F P601-20A R61.F2

[

pre-alarm annunciator exists. i 1 i o Reactor mode switch h ;,ad from panel PEI-1 3.0.2 P680-11E2 Reactor Mode q Switch il .~ 9 o Procedure should capitalize " MODE $= ITCH" to be PEI-1 3.0.2 Procedure consistent with control switch escutcheon. l o There exists no single indicator for 51 power. This PEI-1 3.1.2 P680-11E2 APftM Status nust be determined by 8 independent sources. Lights. [ t i C B-3

[) DETAILED CONTROL R00H DESIGN I EW FINDINGS - TASK ANALYSIS PROCEDURE STEP PANEL EtlUIPMENT MtMut ENGINEERING OBSERVATION NUMBER NtMBER NtMBER NUMBER o ARI controls not currently installed PEI-1 CS3.1.2 P680-11El C22A-S4A P680-11El C22A-54B P680-11El C22A-54C P680-11El C22A-540 o Manual ARI annunciator not currently installed PE!-1 CS3.1.2 P680-5A R61.A3 o Generator breaker simic is incorrect PE!-1 3.1.4 P680-9C S-610-PY-TIE P680-9C S-611-PY-TIE o There is no outstanding indication of the turbine PEI-I CS3.1.4 N/A N/A being tripped. o Turbine step valve position meter nueber 1 is missing. PEI-I CS3.1.4 P680-8B Main Stop Valve Position o There is no turbine shutdown procedure in 50!-N32 PEI-I CS3.1.4 N/A N/A as implied by this step in this procedure. o Na units are indicated on the RECIRC flow rate PEI-1 3.1.6 P680-4B C51-R614 recording meter. o To confirs SLC system operation. operators have been PEI-1 3.1.9.a P601-198 C41-R601 trained to look for decreasing SLC tank level rate of about I scale subdivision per minute. This would be 100 gpa compared to pump capacity of 86 gpm at rated. conditions. Also, relies heavily on operator memory. 8-4 e

1 e-7x. p(/ DETAILED CONTROL ROOM DESIGN view FINDINGS - TASK AMLYSIS () PROCEstmE ST!* PNEL EquipptNT I IW GN ENGIM ERIM WSERTRTION puMBER NtsetR NtmBER IRsWER o RHR flew rate meter label is potentially confusing. PEI-1 3.1.9. P601-208 E12-R603A Label indicates RHR PUMP Flow. Actual reading is b.1 P601-178 E12-R6038 downstream of minimu7m0w recirculation tap. Meter P601-178 E12-R603C indication excludes recirculation flow, o All indicating lights on the P601 isolation matrix are PEI-1 3.1.9.c P601-188 "Close on NS4 similarly colored red for both open and close. The P601-198 isolation standard color, green usually indicates closed. signal"

matrix, o

No 501-G33. RWCU instruction section exists to isolate PEI-I 3.1.9.c Procedure the RWCU system, i.e., identf'y the isolation valves. 3.1.10.c o Inconsistent units are used in the procedure (t) and PEI-1 3.1.9.e P601-198 1C41-R601 control room instrumentation (gal.) for SLC tank CAUTION 1evel. 3.1.9.e o Procedure specifies SLC tank limit of 281. It does PEI-1 3.1.9.e Procedure not specify 28% of what value, i.e., total volume, initial vol me? No procedure currently exists for boron alternate PEI-1 3.1.10.a Procedure o injection. 3.1.10.e Procedure step is written in confusing order. "If-then" PEI-1 3.1.10.c Procedure o statement may be more appropriate than a "Do this - unless" statement. B-5

p y p C,,- f 1 O DETAILED CONTROL ROOM DESIGGVIEW FIN 0!NGS - TASK ANALYSIS i PROCEDINIE STEP PAIEL E9f!PIENT i IWen ENGIIEERilE WSERTATION IRSSER Nt9BER NtMBER IRNWER i o Inconsistent units for boron injection limits exist PEI-1 3.1.10.e P601-198 C41-R601 i between procedure step (pounds of boron) and control room indicators (SLC tank level in gallons) o Green LED lights on the RCIS system display indicate PEI-1 3.1.11.a P680-50 Full Core that both scram valves on a specific HCU are in the Display same position. The system does not differentiate between both valves open and both valves closed. Operator must assume that the normal position after a scram is open. I o Operator receives proper scram valve position indication PEI-1 3.1.11.a P680-50 Full Core in the form of 177 green LED lights on the full core Display i display (FCD). Valves in failed condition are detected by the absence of a green 1ight. It may be difficuit 6 for the operator to find one or two blank lights amidst I the 170 or more green lights in display. I o Identification of fuses in back panels is extremely PEI-I CS3.1. 1H13-P691 1C71-F18A.E poor. Major problem is reinstallation. Only the 11.a 1H13-P692 1C71-F188,F fuse itself is labeled, not the fuse receptacle. 1H13-P693 1C71-F18C.G 1H13-P694 1C71-F180,H Appropriate panel door (i.e. A or B) for fuse access PEI-1 CS3.1. Procedure o is not identified in procedure. 11.a ~ i i B-6 [

s-g DETAILED CONTROL ROOM DESif(' ) VIEW FINDINGS - TASK ANALYSIS PROCEDURE STEP PANEL EQUIPMENT NLMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER o Fuse holder labeling is such that unless detailed PEI-1 CS3.1. 1H13-P691 1C71-F18A.E drawings and wire identification numbers are used 11.a.2 1H13-P692 1C71-F188,F by the operator (no formal training provided) the 1H13-P693 1C71-F18C,G probability of installing a fuse in the wrong 1H13-P694 1C71-F18D H location or of installing the incorrect fuse label is high. o Procedures for termination of boron injection by other PEI-1 3.1.11.c Procedure than normal means are not available. o CRD scram discharge volume high water level bypass PEI-1 3.1.12 P680-5C IC71A-54A j switches are 2 position switches but label plate has IC71A-548 3 positions shown (BYPASS twice) IC71A-54C IC71A-54D o Scram reset logic switches currently out for service PE!-1 ' 3.1.12 N/A N/A o " Scram channel tripped" annunciator windows currently PEI-1 3.1.12 P680-5A R61-C4 labeled incorrectly - planned to be changed R61-04 o Use of RRCS RESET switches is not specified by PEI-1 3.1.12 P680-11El C22-54A instruction task aspect C22-548 C22-54C C22-54D o Panel insert P680-11El new panel design is not PEI-1 3.1.12 P680-11El N/A currently installed. Task analysis was based on paper and pencil design B-7

t-() DETAILEDCONTROLROOMDES!!ClVIEWFINDINGS-TASKANALYSIS PROCEDURE STEP PANEL EQUIPMENT H! MAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER o Turbine first stage pressure permissive limit is not PEI-1 3.1.15 P680-50 RCIS full core indicated on the IURB Ist STAGE PRESSURE recorder. display Operator would refer to this recorder to confirm digital core matrix light operation. I i o Precedure step is out of date. INSERT INHIBIT status PEI-1 C53.1.15 Procedure light serves function of detemir.ing that reactor power is below LO power SET PT, and that control rods are out of sequence. Replaces step of comparing rod positions with table of control rod sequences. Procedure should be rewritten as such, o Jumper cables are not currently available. PEI-1 CS3.1.15 1H13-P629 1C11A-K1 1H13-P618 1C11A-K8 o Labels on relay contacts are obscured by the installed PEI-1 ' CS3.1.15 1H13-P629 1C11A-X1 relays. Operator unable to identify proper relay contacts 1H13-P618 1C11A-K8 S o Relay cculd not be reached by person of average height. PEI-1 CS3.1.15 1H13-P629 1C11A-K1 Acccss to relay within panel is very limited, titus PEI-1 CS3.1.15 1H13-P618 1C11A-K8 increasing the possibility of personnel in. jury or PEI-4 CS3.0.3.a H13-P629 E12-K84 equipment damage as operator tries to gain access. PEI-4 CS3.0.3.a H13-P629 E12-K94 o Identification of panel doors is difficult. Identifi-PEI-1 CS3.1.15 1H13-P629 1C11A-K1 cation of proper panel doors in procedure and labeling 1H13-P618 1C11%-K8 in control room would be helpful. Procedure o No procedure exists for starting a second CRD pump PEI-1 3.1.17a Procedure i C B-8

O DETaitE0C0=Ta0ta00aOESicOvIEvPi=0iaGS-TaSrmaatvSiS (3.- PROCEDURE STEP PAIEL EQUIPIENT IRNGH ENGilEERIM WSERVaTION HL*IBER 1RMBER IRMBER ' 1RNSER o Instrumentation in control room is in units of gallons. PEI-1 3.1.20 P601-198 C41-R601 Procedure specifies decisions based on information in units of % (1 of what is unknown), and pounds of boron o Procedure does not explicitly state to teminate boron PEI-1 3.1.20 Procedure injection before exiting procedure. Only implication is in earlier procedure where boron is injected until 753 lbs is injected. i o Note in section 3.2 could be more appropriately placed PEI-I Note 1 Procedure I i before step 3.2.3 P.12 l Sect.3.2 i o SRV tailpipe pressure switch indicators not currently PEI-1 3.2.1 P601-19C N/A installed. aust reference ONI-821-1 for SRV setpoint PEI-I, CS3.2.1 P601-19C N/A I values, if not connitted to memory. o Reactor pressure setpoint for SRV operation is not PEI-1 CS3.2.1 Procedure 1 yet specified in procedure i i o Procedure does not note the addition of a control PEI-1 3.2.2 Procedure j switch and indication for IPS2-F646 on panel 1H13-P601-2C o Procedure has not been revised since a design change PEI-I 3.2.2 Procedure removed IPS2-F200 from the BOP isolation. Valve i PS2-F200 is being removed from BOP ISOL Group. I B-9

O_ DETAILED'CONTR0t. ROOM.DESICOVIEWFINDINGS-TASKANALYSIS-N[ m PANEL EQUIPENT PROCEDURE STEP, HU4WI ENGINEERING'0BSERVATION NUMBER NUMBER - NUMBER NUMBER .gg ,l \\ l,There is no direct indication of a'30P Isolation PEI-1 .3.2.2 M/A N/A i

zj.

o 'available in the control roomi o The 4 isolation valve controllers / indicators are PEI CS3.2.2. P881 P57-F015A i located on a back panel admidst approximately 75 other a. P881 P57-F020A similar controllers. It is awkward to find the four P882 P57-F015B ( 0 P882 P57-F0208 j "specified valves. o SRV solenoid status lights do not provide direct PEI-1 Note P601-198 N/A j j indication of SRV position. The use of SRV tailpipe. .Pg.14 j pressure switches will provide direct indication. Sect.3.2 i (Tailpipe pressure switch indicators not yet installed) 3 o Procedure step does not include all limits on RPV PEI-1 3.2.3 Procedure -pressure control. Should be; " control RPV pressure 4 below 1033 psig or. the heat capacity temperature limit i with the main turbine bypass valves. I ly o Pressure recorder used for'RPV pressure control feedback PEI-1 3.2.3 P680-7C C34-R609 i l is a 2 scale recorder, color coded red and blue. Color -legend is not defined on. instrument. Operator can not i tell which indication to read. i RPV pressure recorder can not be' read from controller PEI-1 3.2.3 P680-7C t34-R609 o { position. i i i e i I B-10 l e v- -..-- a

h DETAILED CON ROL ROOM IESIC VIEW FINDIES - TASK ANALYSIS PROCEDURE STEP PANEL. EQUIPMENT-HINWI EMINEERING OBSERVATION NUMBER NUMBER IRMBER 1RMBER o ' Procedure step implies greater accuracy than pressure PEI 3.2.4.a. P601-178 821-R6238 recorder can provide. Operator cannot detennine 1033 P601-208 B21-T623A setpoint on recorder. -He only has to stabilize pressure somewhere below 1033 psig. Procedure implies excessive g accuracy. o Procedure does not specify operation mode from RWCU PEI-1 3.2.4.b Procedure o Procedure step is not specific concerning the rate of PEI-1 3.2.6.a Procedure 1 vessel depressurization the operator is to produce. l o .There is no simple, direct indication of MSIV-PEI-1 3.3.2 N/A N/A isolation logic status. Any one of 22 annunciators located in various locations around the control ) room could indicate MSIV isolation logic should have tripped. I o There is no direct indication of RCIC automatic PEI-1 3.3.2 N/A N/A 1 initiation logic trip, which is required for this task. Logic initiation can only be inferred from l HPCS logic trip which should correspond to RCIC logic. i i I Loop C VPI RHR Test valve to SUPR PL does not have PEI-1 3.3.2 P601-2 R603A l 0 l manual override-indicating light. Loops A and B do. i o RPV water level recorder / meters are not labeled with PEI-1 3.3.3 P601-208 821-T623A l colored bands.to demark 15" and 50" limits. Alarms P601-178 821-R6238 will infonn the operator he is outside the desired P680-38 C34-R608 l range (notapproachinglimits). l 8-11

DETAILED CONTROL ROOM DESI hEVIEW FINDINGS - TASK ANALYSIS h_. PROCEDURE STEP PANEL EQUIPMENT HUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER o CST tank level recorder has no units on scale. CST PEI-1 Caution P870-28 N21-R203 tank level is included on a 2. function recorder. Color-1 Pg.21 coded legend is not specified. Proper color must be Sect.3.3 remembered by operator. o Drywell pressure indication of 2 psig could not be read PEI-1 Caution P601-17B D23-R0468 on the meter. The meter scale is in psia while the 2 Pg.21 P601-208 D23-R046A procedure specifies psig. Sect.3.3 o Wording of caution is very confusing when referring PEI-1 Caution Procedure to maximum injection pressure. Could be worded to 2 Pg.21 better describe the intent. The purpose for this Sect.3.3 caution is not obvious (thermal shock considerations). if The purpose should be. incorporated into the caution somehow. o All meters and recorders do not state reference O PEI-1 .Al-1 P601-178 B21-R6238 elevation which is different for different instruments P601-208 B21-R623A P601-17B B21-R610 P601-208 B21-R615 o Inconsistent reference 0 elevations for water level PEI-1 Al-1 P601-178 B21-R623B instruments P601-20B B21-R623B P601-178 821-R610 P601-208 B21-R615 l o HPCS flow has same range as other injection subsystems, PEI-1 Al-2 missing missing l however units are different (GPM x 10 vs. GPM x 100) l l l B-12

t {} DETAILEDCONTROLROOMDESirgiVIEWFINDINGS-TASKANALYSIS PROCEDURE STEP PANEL EQUIPMENT HUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER l Full range of RPV level when below - 145" (FZR & WR) PEI-1 Al-2 missing missing 0 l cannot be compared since references differ. Requires l mental calculation by operator. A common reference point (top of active fuel) will be used for all ranges of level indication. o Feedwater flow recorder does not have process units PEI-1 Al-2 P680-3B C34-R607 identified on meters. Scale multiplier is not identified either, 7 o PEI should use the same nomenclature for RHR system PEI-1 Al-CS2 Procedure cross tie as 501 (RHR Loop B containment flood mode) o Procedure does not indicate that ADS logic reset must PEI-1 Al-3 Procedure be reset at least every 105 seconds to inhibit ADS f o Operator cannot correlate fuel zone and wide range PEI-1 AI-3 P601-17B B21-R623B levels without a mental calculation due to different P601-208 B21-R623A zero reference points. Note the --160" on WR equals P601-17B B21-R610 + 7" on FZ, and 182" above TAF is + 15" on WR. P601-20B B21-R615 lPEI-1 Al-3 P601-208 B21-R615 Only 1 fuel zone water level recorder is' available o Operator has no digital indication when 105 second PEI-1 Al-3 N/A N/A ' o ADS timer is running out. A timer and possibly early warning annunciator for impending ADS may be helpful. B-13 }

,a ^ x unan u.cu uuninuu nuvo u s.o u - au. ..m..m, PROCEDURE STEP . PANEL EQUIPMER NUMBER NUMBER NUMBER NUMBER HUMAN ENGINEERING OBSERVATION PEI Al-3 P601-17B B21-R623B Specifying WR indication in procedure step seems to o restrict operator from using fuel zone range. Note P601-20B B21-R623A that at -148" the wide range recorders are at bottom of scale. - 148 can not be read on recorder scale since discrimination is 2 1/2 - units.- Operator will rely on level 1 annunciator for positive indication, Operator could be confused by blank space in table for PEI-1 Al-3 Proedure o this procedure step. " Step 7" should be centered under the two pressure ranges to which it applies. PEI-1 Al-4 Procedure Specifying the first step, " step 3.3.1" of the referred o section, seems trivial and superflous. PEI-1 CSAl-5.s Al-6B i Process units are not shown on pressure recorders. PEI-1 Al-5.a P601-17B B21-R623A o P601-20B B21-R623B Procedure step 6.a was noted by operator as hard PEI-1 A-6a Procedure o to read. He read it twice to fully comprehend it. Suggest using semicolons to improve punctuation, There is a discrepancy in nomenclature between PEI-1 Al-7.c. Procedure o step Al-7c and Al-7.d.1). Step Al-7.d.1 lists Al-7.d.1) RHR A,B,C whereas step Al-7.c lists LPCI A.B.C. The two parts of the procedure should be mada consistent. B-14

) LC idLC; CG;;n0L 20= 0CCIhC"!:" !!"*"'OC ^ TA C " A " A'." "! O PROCEDURE STEP PANEL EQUI h m HtRfAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER "RPV water" conid be more clearly specified as "RPV PEI-1 Al-8.a. Procedure o water level" b,c Wording in procedure should be " ADS valves" instead PEI-1 Al-9 Procedure o of " ADS valve", Procedure does not specify possible injection flow PEI-1 Al-11 Procedure o paths referred to as " injection into the RPV from sources external to the primary containment" PEI-1 Al-11 Procedure No procedures exist covering the alternate injection o modes. Control from outside the control room is required. -145" setpoint on RPV. water level recorder is not color PEI-1 Al-2 P601-17B B21-R623B o P601-20B B21-R623A coded or otherwise uniquely identified, but can be determined from recorder scale. Procedure does not appear to consider possibility of FW PEI-1 'A2-CSla. Procedure o flow to RPV from RFBP if RPV pressure is less than 1 RFBP shutoff head, Typographical error in procedure step " System" should PEI-1 A2-CS. Procedure o 1.a.2 be " systems" PEI-1 A2-CSA. Procedure Operator action was different from procedure step o description. Operator did not adjust the flow setpoint 1.a.3) as specified by the procedure. He used the "CLOSE" button on the controller to adjust the controller flow output. B-15

h.. h DETAILED CON ROL ROOM DESI EVIEW FINDINGS , TASK ANALYSIS PROCEDURE STEP PANEL EQUIPMENT. HtMAN ENGINEERING 0BSERVATION NUMBER NUMBER NUMBER MUMBER o -Typographical error in.the procedure step. Several PEI-1 A2-CSI. Procedure-1 lines of text have been deleted from the procedure a.4 o-Range 'of suppression pool water level recorders is PEI-1 A2-2 P883 1G43-R073A insufficient for procedure step. Reference zero for P883 1G43-R073B i instruments is 18'2" and lowest indicated level possible is 12'2". The 8 f t level required by the ] procedure cannot be determined from the instruments. o RPV pressure steam cooling limit (700 psig) is not PEI-1 A3-2 P601-20 B21-R623A 4 banded or coded on the RPV pressure recorders. The P601-17 B21-R623B { .value can be read off the meter if monitored. i o SRV solenoid status light is not a direct indication PEI-1 A4-1 P601-19C SRV solenoid of valve position; it reflects a demand signal only. PEI-2, 3.0.2 "A" status (19) The tailpipe pressure switches (not yet installed) PEI-2 CS3.2.2 P601-19B SRV solenoid will provide a direct indication and will be suitable. "B" status (19) o The MSIV control switch has "CLOSE" position on right PEI-1 A4-2 P601-18C B21-F022A t side of escutcheon (clockwise rotation). All others in P601-18C B21-F0228 l control room have "CLOSE" position on left (counter-P601-18C B21-F022C ~ clockwise rotation). Violates control room convention. P601-18C B21-F022D i L o The order in which the procedure lists valves which are PEI-1 A4-2 Procedure to be closed does not minimize distance operator must walk. Listing valve 821-F016 first in procedure step would minimize the distance that the operator must walk. B21-F016 is in the proximity of the MSIV controls-whereas E51-F063 is about 10 feet away. I B-16 i

W 0"* ^ ?t= ' c=T=^t "a= 9'c M mme n w e _ wace awarvm e PROCEDURE STEP PANEL EQUIPMEFf NtRfAN ENGINEERING OBSERVATION . NUMBER-NUMBER-NUMBER NUMBER o PEI does not use same nomenclature as the SOI for PEI-1 A4-4 Procedure RHR " containment flood" operating mode. PEI-1 A4-10.a o Inconsistent scale multipliers are used on HPCS flow PEI-1 A4-4 missing missing meter (0-100x10) and RHR A,B.C flow meters (0-100x100) o The minimum alternate RPV flooding pressure values for PEI-1 A4.5.a P601-17B B21-R6238 the number of SRV's open are specified to a degree P601-20B B21-R623A of accuracy four times more accurate than the resolution of the reactor pressure wide range recorder scale. o Caution should be more explicit in its message, i.e., PEI-1 Caution Procedure avoid rapid increases of injection flow. Other cautions Pg. 37 (i.e. CAUTION pg. 31, attachment 2 following A2.2) arn atta. 4 of the nature it is acceptable to violate normal limits (such as 100*F/hr cool down). This caution does not specify the acceptability of such cautions. o Procedure instruction is confusing. It is not clear PEI-1 A4-5.c Procedure what the phrase "at least" is referring to. o The end of the task is not clear. There is no PEI-1 A4.5.d Procedure terminating cue given. Operator is not told when to stop " Maintaining." o Procedure step is vaguely worded. Instruction states PEI-1 A4-6.e. Procedure that operator is to " slowly" increase RPV water level. A4-7a.4) N/A N/A " Slowly" is not quantified. Presently, no direct rate A4-8.a. indic~ation for " slowly" raising RPV level exists. .4) B-17

nr rut rn enarrant-nnnu nFRTC TRU FTNDTNCE - TAME ANAf39fS PROCEDURE STEP PANEL EQUIPMElfr ~' NUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER e The sentence, " Perform the following actions", could PEI-1 A4-7.a Procedure l o be deleted to maintain the same format as step A4-6. A4-8.a A4-9.a A4-10.a No procedure exists for HPCS test mode to suppression PEI-1 A4-7.a.2 Procedure o pool. t Four panel doors per panel must be checked by operatnr PEI-1 A4.8.a.1 Procedure o to find correct one. Specification of panel door PEI-4 CS3.0.3. t number in procedure would help operator find correct a relay quickly, No SOI procedure exists for LPCS test mode start PEI-1 A4-8.a. Procedure o 2) LPCS pump ammeter has non-standard scale graduations. PEI-1 A4.8.a. P601-21B E21-R100 o Craduations are at 6 amp intervals with highlights 2) at 30 amp intervals and numbers at 60 amp intervals. RHR pump ammeter has non-standard scale graduations. PEI-1 A4.9.a P601-17B 1E12-R100C o 3 amp increments are used. Procedure step is vaguely worded. RHR valve is to be PEI-1 A4-9.a.4 Procedure o " slowly" throttled, but " slowly" is not quanitified. Operator is required to compare RPV pressure in psjtjt PEI-1 A4-12.a P601-17B B21-R6238 o to containment pressure in psia and determine the PEI-1 A4-CS14. P601-20B B21-R623A pressure difference - Inconsistent process units, b P601-17B D23-R024B P601-20B D23-R024A i i i i B-18 l

l- /~xU DETAILED CONTROL ROOM DESIC J CVIEW FINDINGS - TE K ANALYSIS PROCEDURE STEP PANEL EQUIPMENT HUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER The "or" logic in the procedure step is inappropriate PEI-1 A4-14a Procedure o for substep 3) since steps 5 through 12, preceding this step, have already been accomplished in part. Step 14.a.2) is confusing in that it is writtin PEI-1 A4-14a Procedure o as a comand implying control action. It is actually a check or verification that steam is condensing to fill reference leg. Operator takes no action to perfonn this task, o Containment temperature recorder / meters have non-PEI-1 A4-14.b P883 1023-R170A P883 1023-R1708 i standard 2 1/2 F scale increments Top of vessel is not identified on the SHUTDOWN PEI-1 A4-CS14. P601-17 B21-R605 o RANGE WL meter. Operator is required to find b 3 j vessel height and calculate from instrument zero or remember. 3 j Operator used range of level instrumentation with PEI-1 A4-14d. Procedure o only one channel available. Procedure provides no guidance as to how to reduce water level and which instruments to monitor for response. The SRV taps (MS Lines) are at an elevation higher than top of wide range instrumentation. Should the operator attempt to drain below the Main Steam Line if Shutdown Range does not provide proper response? Procedure is not clear, and this was not discussed in the i i operator's training. B-19 k

.r uniniLEL Cunin6L Reun LE54 Acutin iinuinus - -non annu aio PROCEDURE STEP PANEL EQUI L _. NUMBER NUMBER NUMBER NUMBER NUMAN ENGINEERING OBSERVATION PEI-1 Note 2 Procedure First page note of attachment 5 pertains to a o subset of the attachment steps (9 out of 17 steps). Pg.53 The note may be overlooked during the execution of Atta.5 the PEI's when the operator would be carrying out steps spatially removed from this note. I Procedure step instruction may be confusing the PEI-1 AS-4.a Procedure i o way it is written. The instruction says to take specific, discrete actions (e.g. terminate injection except boron and CRD) until one of the three conditions is met. The until statement usually implies that a continuous control process is discontinued at the specified time cg; to return the system to its previous state at the specified time. Neither is the intent of this statement. The intent is that the operator monitor and wait to take further action until the condition is met. Use of a consistent format throughout the instructions PEI-1 AS-4.b Procedure o '& c for this type of instruction would help readability. Other similar instructions in the procedures are written as; when one of the following conditions is satisfied, then (perform the action). i Condition 1 Condition 2 etc. i as opposed to this format; when one of the following conditions is satisfied; i Condition 1 Condition 2 etc. (p'erform the action) One format should be followed throughout if possible. B-20

DETAILEDCONROL~R0OMDESIOEvlEvr!N0iNc5?TASxaNAtv5IS-d. PROCEDURE STEP PANEL EQUIPMENT NUMAN EMINEERING OBSERVATION NUMBER NUMBER NUMBER' NUMBER o Minimum reactor power level is not specified in the PEI A5-13 Procedure procedure. Operator was told 10% in training session, o Procedure step specifies water level of -145 inches, PEI-1 A5-CS16 Procedure but with no reference, (Fuel Zone / Wide Range?) o No units are indicated on Fuel Zone Level Recorder PEI Several: P601-208 821-R615 3.3 caution 2 Attach. 4-15 o RPV Level / Pressure Recorder A is not labeled in any way. PEI-1 Several: P601-208 Not labeled 3.3 but probably caution 2 B21-R623A 3.1.b.1 Attach. 4-15 o RPV Level / Pressure Recorder has awkward, non-standard PEI-1 Several: P601-178 B21-R6238 highlightfag of level scale 2.5, 5, 25, 50 3.3 P601-208 Not labeled Caution 2 but probably 3.1.b.1 B21-R623A Attach. 4-15 9 r B-21

c x (j mut-a ca=?=^t =^^= nec t. _ rurru wrunruce vinr Awavytts PROCEDURE STEP PANEL EQUIPMENT f NtRfAN ENGINEERING OBSERVATION NUMBER NUM8ER NUMBER NUMBER f o Reference elevations for water level instrumentation PEI-1 Several: P601-208 B21-R615 l are not indicated on the instruments. The reference 3.3 'P601-20B B21-R623A l elevation is different for different instrument. CAUTION P601-17B B21-R6235 f2 P601-178 B21-R610 3.1.b.1 g Att.4-15 l Operator is given no clear guidance as to what flow PEI-1 Several: Procedure o { rate is " adequate" for LPCS or llPCS core cooling 3.3 CAUTION

1. 2 l

3.1.b.1 Att.4-15 Suppression pool temperature meter does not indicate PEI-2 2.0 P601 D23-R220B o setpoint PEI-2 3.0.4 P601 D23-R220A Suppression pool temperature meter is for one selectable PEI-2 2.0 P601 D23-R2208 o channel out of 8. Operator should go to recorder, not PEI-2, 3.0.4 P601 D23-R220A j meter. No alert for the operator is indicated on the PEI-2 3.0.5 label or in the procedure. j Suppression pool high temperature _ annunciators are PEI-2 2.0 P601-20A R61. G3 o in different positions in annunciator matrix PEI-2 3.0.4 P601-17A R61. F2 Suppression pool temperature recorder glass covera PEI-2 2.0 P883 1D23-R090A f o are frosted so that recorder / meter is obscured. PEI-2 3.0.2 P883 1D23-R090B i PEI-2 3.0.4 PEI-2 3.0.5 Confusion in setpoints of SRV's. Operator could not PEI-2 3.0.2 P601-19C N/A o remember closing setpoint which has changed. Setpoints f are not indicated on panels. There are plans to identify setpoints on control switch escutcheons, i B-22

h DETAILED CON ROL.ROON DESICOv= ri=i=5 - TASx ANauSiS 6, PROCEDURE STEP PANEL EQUIPfENT .N IU MN ENGINEERINE OBSERVATION NUMBER NLMBER IRMBER 1RMBER. 1 l o Steam tables should be part of' documentation available PEI-2 3.0.2 N/A N/A - 1 in control room in order for operator to determine j-adiabatic expansion temperature for determining l steam leakage through S/RV. o The supporting instruction to this step directs a PEI-2 '3.0.2 Procedure Fast Reactor Shutdown, but PEI-2, CS 3.0.2 does not direct this until 2 minutes elapse. This is a discrepancy. o OMI associated with this task is not explicitly PEI-2 3.0.2 Procedure referenced in the procedure step. i i o Digital clock is not yet in place. (Itshould PEI-2 CS3.0.2 N/A N/A include seconds in display to allow operator to discriminate 2 minutes, which is a Tech. } Spec. requirement (standard)). Clock with i timing function would be desirable. 4 i l o Operator cannot use recirculation flow control PEI-2 CS3.0.2a P680-4 B33-K601 valves master controller to reduce flow below P680-4 B33-K602 l 48% actual flow (26% valve position indication). P680-4 B33-K603A Control must be in flux manual (or lower control) P680-4 B33-K6038 to decrease below 487, actual flow because of-low Procedure flow stop. j o Operator cannot bring valve position down to 0% on the PEI-2 CS3.0.2a P680-4 B33-K603A i scale. Minimum position will actually be at 22%.. P680-4 B33-K603B Valve indicated position of 0% is equal to 22% Procedure actual flow position. f B-23 3 + ,r

l' () DETAILEDCONTROLROOMDESIdllhiVIEWFINDINGS-TASKANALYSIS ll PROCEDURE STEP PANEL EQUIPMENT HUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER o NPSH requirements are not available as specified PEI-2 Caution Procedure by procedure CAUTION. o Suppression pool water level scale is in feet PEI-2 3.0.5 P601-17 G43-R062A referenced from 593 ft MSL (above mean sea level). P601-20 G43-R0628 Heat Capacity Temperature Limit curve is in feet P883 G43-R073A referenced from the bottom of the suppression P883 G43-R073B pool. Operator must perform conversion in order to compare meter reading to plot. o Suppression pool level recorders / meters have insufficient PEI-2 3.0.5 P601-17 G43-R062A ranges. A range of 18 to 42 feet is included in the P601-20 G43-R0628 plot of Heat Capacity Temperature Limit in the procedure. P883 G43-R073A The wide range level recorder's range is -6 to +6 feet P883 G43-R0738 referenced to 593' MSL. o lack of grid lines on graph of Heat Capacity Temperature PEI-2 '3.0.5 Procedure Limit hinders readability of chart. o Wording of procedure step implies that it is allowable PEI-2 3.0.5 Procedure to (temporarily) maintain suppression pool temperature above the Heat Capacity Temperature Limit before directing control of RPV pressure. o Drywell temperature recorder has incorrect point PEI-3 2.0 P883 023'R170A identification label affixed to front. B-24

.m. g p b DETAILEDCONTROLROOMDESItMEVIEWFINDINGS-TASKANALYSIS a 4 PROCEDURE STEP PANEL EQUIPMENT HUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER High drywell temperature setpoint is not yet identified PEI-3 2.0 P601-20A R61.F3 o in procedure. Annuncitoar setpoints may or may not P601-17A R61, R5 identify entry condition. Procedure o Drywell temprature meters and recorders do not PEI-3 2.0 P601 D23-R210A have required range as specified by RG1.97. P601 023-R210B P883 D23-R170A P883 D23-R170B o There is no single alarm to identify a balance PEI-3 CS3.0.2 N/A N/A of plant isolation PEI-4 CS3.0.2 o Annunciator for CNTMT/DW ISOL RPV Level 2 presently PEI-3 CS3.0.2 missing missing alarus on RPV level 1. o BOP isolation matrix lights are color coded PEI-3 CS3.0.2.a P601-188 B21-533 differently from the control room convention. P601-19B B21-532 Closed valve is indicated by amber light as opposed to green for the rest of the control room. o No BOP Isolation reset indicator is available. PEI-3 CS3.0.2.a N/A N/A o Procedure does not elaborate on " maintain". Operator PEI-3 3.0.3 Procedure may not be aware of all methods. Drywell temperature treters do not support full PEI-3 3.0.3 P601 D23-R210A o P601 023-R210B range of procedure attachment 2 graph. B-25

l-li () DETAILEDCONTROLROOMDESIGlllVIEWFINDINGS-TASKANALYSIS PROCEDURE STEP

PANEL, EQUIPMENT HUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER Confusion was noted on the labeling of the y-axis of PEI-3 CS3.0.3 Procedure o

attachment 2 to the procedure. It may be more appro-priate to label this axis as the drywell temperature since this is the variable that the operator is monitoring, Lack of grid lines on procedure PEI-3 attachment PEI-3 CS3.0.3 Procedure o 2, "RPV Saturation Temperature vs. Saturation Pressure" plot, hinders readability of graph. No further control of the system is possible following PEI-3 3.0.4 Procedure o step 3.0.2. Procedure step could be replaced with the PEI-3 CS3.0.4 Procedure contingency step and revised so that " maintain" becomes " verify". Containment temperature meters have different scales. PEI-4 2.0 P601-178 D23-R200A R200A is 50-350*F while R200B is 50 to 200*F. PEI-4 3 0.3 P601-208 D23-R2008 o i Containment temperature entry condition is not PEI-4 2.0 Procedure o PEI-4 3.0.2 Procedure yet specified in procedure. Indication of BOP isolation is not very salient. PEI-4 CS3.0.2 P601-188 P50-F140 i ,,60-F060 o P P601-198 The positions of chilled water valve status lights i in matrix differ from panels 601-188 and P601-19B. Indicators P50-F150 and P60-F060 in P601-19B matrix are in reverse numerical order. i B-26 s l i

~ O DEmiuo CONTR0t ROOM oEs1 OviE nN0ims - uso usis D. PROCEDURE STEP PANEL EQUIPMENT MUMAN E MINEERI M OBSERVATION NUMBER NUMBER NUMBER NUMBER o Containment pressure meters and recorders are in PEI-4 3.0.3 P601-208 D23-R024A units of psia while procedure specifies values in p g. PEl-5 Caution P601-17B D23-R2048 Operator must convert units mentally. Pg.1 P883 D23-R180A PEI-5 3.0.3 P883 D23-R180B PEI-5 3.0.6 Att.4 o Procedure specifies a containment pressure setpoint .PEI-4 3.0.3 P601-20B D23-R024A of 1.65 psig for spray initiation. Containment P601-17B D23-R024B pressure meter scale resolution is 0.5 psig. Operator Procedure would not be able to discriminate 1.65 psig to the accuracy requirement of.05 psi implied by the procedure. o Procedure specifies a drywell pressure setpoint in PEI-4 Cs3.0.3 P601-17B D23-R046A units of psig. Drywell pressure meter and recorder PEI-5 2.0 P601-208 D34-R046B i P883 D23-R180A scales are in units of psia. Operator must convert units mentally. P883 D23-R180B l P o Back panel doors are labeled only with temporary tape. PEI-4 Cs3.0.3.a P629 Door C (Generic) o Jumper cables were not available to test, but this PEI-4 Cs3.0.3.s N/A N/A appears to be a difficult task. Under stress, this is an unreasonable task. Also, this promotes potential error. I o Use of the term " maintain" in this procedure step is PEI-4 3.0.4 Procedure 1 vague because no method for " maintaining" is.provided. PEI-4 3.0.5 i l i u B-27 j i

t-O oETartto coaTaot ao0a oEst OviEw riaotaos - Tasx ana'vsis 4-PROCEDURE STEP PANEL EQUIPMENT HtNAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER o Drywell pressure value for entry condition is not PEI-5 2.0 Procedure yet specified in the procedure. Annunciator may or P680-5A R61, A-5 may not correspond to entry condition. o Installed RCIC turbine exahust pressure meter range PEI-5 Caution P601-21B E51-R603 does not correspond to system design specification Pg.1 range of 0-100 psig. Installed meter has range of 0-200 psig. o RCIC pump discharge pressure meter has awkward, PEI-5 Caution P601-218 E51-R601 non-standard scale markings of 0,30,60,90.... Pg. 1 with 15 minor divisions between majors. Standard i is 10 minor divisions between majors, and major increments of 1,2 or 5 or multiples thereof. o CAUTION statement is too vague. It does not indicate PEI-5 Caution Procedure whether or not the consequence of an RCIC turbine trip Pg. 1 b is acceptable. The caution is useless unless it states I. acceptability of the consequences. l o Drywell pressure value for operation of drywell cooling PEI-5 3.0.2.a Procedure I system is not specified. Suitability of drywell pressure meter can not be evaluated. o Containment pressure meters and recorders have PEI-5 3.0.2.b P601-20B 023-1024A inadequate range for procedure step. Required range P601-17B D23-R024B is -10 in. Hg to 60 psig. Current range is 10 to 35 P883 023-R180A l i psia.' P883 023-R180B t r i B-28

'([ DETAILEDCONTROLLROOMDESIGhVIEWFINDINGS-TASKANALYSIS.h. PROCEDURE STEP PANEL ~ EQUIPMENT IRMut ENGINEERIE OBSERVATION NUMBER NUMBER 1RMBER NUMBER i o NPSH curves (Attachment 1 to procedure PEI-5) are not PEI Caution Procedure yet available in procedure. Suitability of instru-i i mentation can not be determined until the curves are available. i o Use of the tem " maintain" in this step may more appro-PEI-5 3.0.3 Procedure priately be " verify". A contingency step may be more PEI-5 3.0.5 i appropriate also. PEI-5 3.0.6 i PEI-5 3.0.7 i i o lack of grid lines on Pressure Suppression Pressure Limit PEI-5 3.0.3 Procedure curve (PEI-5, Attachment 2) hinders readability of plot. (Att.2) i j l o Installed suppression pool / upper pool level instruments rf4-5 3.0.3 P601-208 G43-R062A 1. do not satisfy range requirements. Current instruments P601-17B G43-R0628 have range of -6 to +6 ft above normal water level. P883 G43-R073A Required range is 16 to 36 ft above pool floor. P883 G43-R0738 1 Procedure i i o Installed suppression pool level instruments have range PEI-5 3.0.5 P601-208 G43-R062A of -6 to +6 f t above NWL (18'2" above pool floor). (Att. P601-178 G43-R0628 Attachments 3 and 4 from PEl-5 have plots which include 3,4) P883 G43-R073A water levels of 10 to 50 ft. above pool floor. Instru-P883 G43-R0738 mentation range is inadequate. Procedure o Containment pressure in Attachment 4 to procedure PEI-5 PEI-5 3.0.6 P601-208 D23-R024A ranges from 10 to 60 psig. Existing instrumentation has P601-17B D23-R0248 range to only 30 psia. Range of instruments does-not Procedure include range of procedure step. 4 } B-29 jT i I

b DETAILEDCONTROLROOMDESILC2VIEWFINDINGS-TASKANALYSIS g l t PROCEDURE STEP PANEL EQUIPMENT [ HUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER Suppression pool level instrumentation is in units PEI-6 2.0.1 P601-20B G43-R062A o of feet only. Procedure specifies ft and inches. PEI-6 CS3.0.1 P601-178 G43-R0628 Units do not correspond. PEI-6 3.0.6 P883 G43-R073A PEI-6 3.0.7. P883 G43-R073B a&b Procedure Suppression pool water level scales on instruments PEI-6 2.0.1 P601-20B G43-R062A o are not color coded to show setpoint PEI-6 2.0.2 P601-178 G43-R0628 PEI-6 CS3.0.1 P883 G43-R073A P883 G43-R073B Procedure Procedure Step CS3.0.1 could be eliminated and let PEI-6 CS3.0.1 Procedure o the following conditional jumps handle the PEI-6 CS3.0.1.a branching requirements - in the procedure steps column. PEI-6 CS3.0.1.b s There are disagreements between the procedure and panel PEI-6 3.0.2.a Procedure o nomenclature. Procedure could include panel label (501-P11 P870-2C P11-F110 verbatim " CST ALTN SUPPLY FROM MIXED BED WATER" for S.4) better understanding, CST level and Hotwell level are recorded on a 2 pen PEI-6 Caution Procedure o P870-2B N21-R203 recorder which does not have labels to identify which pen and parameter correspond. Units are not labeled. Procedure does not as yet specify units or value for CST level setpoint, but tech. spec, is in gallons. Suit-ability could not be determined at time of review due to lack of this information. B-30

O DETAltEoC0a?ROLROOMDESIC2viErInoInGS-1ASxA=AtvSIS(j. PROCEDURE STEP PANEL EQUIPMENT HUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER o There is no consistency in the positioning of PEI-6 CS3.0.4 P601-20A R61, 02 raleted annunciators within the matrix. P601-17A R61. D1 P601-20A R61. E2 4 P601-17A R61. El i P601-20A R61. F2 i P601-17A R61. F1 o Train A indicator for Sep. P1 Lvl is mislabeled - PEI-6 CS3.0.4 P601-208 G43-R022A Fuel Strg P1 Lyl. After reviewing print, operator F501-178 G43-R0228 concluded indicator should be labeled Sep Pl Lvl A. i i o Suppression Pool Makeup System was abbreviated SPMS PEI-6 NOTE Procedure t in this procedure step. This is the only place such abbreviation was used in the entire procedure. o Suppression pool level range specified in procedure PEI-6 3.0.7. Procedure is greater than the range of the instrumentation a.& b P883 G43-R073A j Procedure (PEI-6, 3.0.7, Attach 2): 18-40 ft. (Att.2) P883 G43-R0738 [ j Instrumentation

12'2"-24'2" i

i I o Pressure Control Limit graph (Attachment 2 to PEI-6) PEI-6 3.0.7 Procedure would be easier to read with grid lines. a&b 2 Cooldown rate in procedure caution has incorrect units PEI-6 Caution Procedure o j of 'F. Time unit for rate is missing. i i I o Containment water level is not specified in procedure PEI-6 3.0.11 Procedure i i yet. Suitability can not be determined. e !T B-31 j ~

Ill () DETAILEDCONTROLROOMDESIC{ll[VIEWFINDINGS-TASKANALYSIS PROCEDURE STEP PANEL EQUIPMENT HUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER Procedure step can vary depending on the state of PEI-6 3.C.11 Procedure o the plant and requires extensive operator knowledge and memory. It may be helpful to have a list of possible systems and actions to use as a checklist. Although procedure says " terminate", operator interpreted PEI-6 3.0.11 Procedure o this task as, " change source to internal from external where applicable". Procedure wording can be confusing. The three radiation monitors specified by the procedure PEI-7 2.0.1 Procedure P804 D17-K836 o are located at various positions in a matrix of 28 similar meters. Better identification of location would P804 D17-K786 P804 D17-K856 help operator respond faster. Procedure does not yet specify gaseous effluent release PEI-7 2.0.1 P804 017-K836 P804 D17-K786 o radiation level setpoint. Suitability of radiation P804 D17-K856 monitors can not be determined. Procedure i Procedure does not yet specify liquid effluent release PEI-7 2.0.2 P906 D17-K821A P906 D17-K821B o radiation level setpoint. Suitability of radiation P604 D17-K604 monitors can not be determined. P604 D17-K605 P906 D17-K606 Procedure h B-32

N - - ~ =. = - PROCEDURE STEP PANEL EQUIPMENT NUMBER NUMBER NUMBER NUMBER NUMAN ENGINEERING OBSERVATION PEI-7 3.0.1 Procedure Procedure is too vague concerning statement to o " isolate all primary systems that are discharging radioactivity..." A list of systems which could fall into this category may be an appropriate attachment to the procedure. PEI-7 3.0.1 Procedure Guidance on isolation procedure for the various o systems is lacking. PEI-7 3.0.1 P601-19B Containment Isolation matrices on P601 are not arranged to P601-18B Isolation o best identify isolation groups. matrix i 4 i B-33

EL ;_.__ _ _........... _ .:..____ m :..:

o ATTACHMENT C DETAILED CONTROL ROOM DESIGN REVIEW FINDINGS TASK ANALYSIS - 101s.,

O O

DETAILED CON ROL ROOM DESit EVIEW FINDINGS - TASK ANALYSIS = PROCEDURE STEP PANEL EQUIPMENT NUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER o Task is not performed at remote shutdown panel. 101-11 4.1.1 Not I Operations are performed locally by roving 101-11 4.1.2 Applicable operators. No task analysis performed since 101-11 4.2.4 task is not related to control room function. 101-11 4.4.2.1 RADIO COPMUNICATIONS SHOULD BE AVAILABLE ANO 101-11 4.4.2.2 CHECKED DETWEEN REMOTE SHUTDOWN PANEL AND ROVING 101-11 4.4.2.3 OPERATOR. 101-11 4.6.2.3 o RPV level recorder (not meter) has non-standard 101-11 4.1.3 P001 C61-R012 scale graduations of 3 inches. o RPV level recorder / meter has no MPL number listed 101-11 4.1.3 P001 C61-R010 on nameplate. P001 C61-R012 o Transfer switches are improperly labeled. 101-11, 4.2.1 P001 C61-5102 P001 C61-511 P001 C61-S107 P001 C61-5100 i o Operator verified power to Bailey Recorders by verifying 101-11 4.2.2 Procedure t chart drive operation. This is not noted in the procedure, o Procedure references non-existent Attachment 6. 101-11 4.2.3 Procedure o No valves applicable to Div. 2 Remote Shutdown 101-11 4.2.3 Procedure included in 101. t e I E l C-1

i O oEraitEoC0 air 0tR00moEsit CiEWrInolaos-TasxanatvsIs d. L t PROCEDURE STEP PANEL EQUIPMENT WINWI ENGINEERING OBSERVATION NUMBER MUMBER NUMBER NUMBER }! o Confusion could occur due to similar MPL numbers 101-11 4.3.3 P001 P42-C001A i., for ECC and EsW pump A start switches P001 P42-C0018 l 4 ,i o Task analysis was performed on "as designed" basis. 101-11 4.3.1 j.' 101-11 4.3.2 MCC EFIC12 P45-F1308 i Compt H 101-11 4.3.2 EH1205 P45-C0018 101-11 4.3.3 R23-s012 P42-C0018 t i EFID i, 101-11 4.3.3 P002 P42-R0458 1 I 101-11 4.3.4 MCC EF1007 E12-F0048 h';iil i Camp F 101-11 4.3.5 MCC EF1007 E12-F0478 2 i Camp U l, l 10I-11 4.3.6 MCC EF1007 E12-F0038 l-l l Comp D i 101-11, 4.3.7 EFID07-E12-F0648

1. t Camp CC F

101-11 4.3.8 EH1208 E12-C0028 p /[l i Comp T 101-11 4.3.8 P001 CSI-R025 101-11 4.3.9 EF1007 E12-F0248 d ', l Comp M 101-11 4.3.10 P002 C61-R025 j 101-11 4.3.10 EF1007 E12-F0648 Comp CC l l 101-11 4.3.11 EFID07 E12-F0488 L l Comp V t i 101-11 4.3.12 P002 C614t025 l 101-11 4.3.12 MCC E12-F0038 EF1007-D 101-11 4.3.12 P002 D23-R270

. 7' j

i I e I l C-2 l 1 i

~ FMM - M MMS. . l' PROCEDURE STEP PANEL -EQUIPMENT li HUMAN ENGINEERING SBSERVATION-NUMBER NUMBER NUMBER. NUMBER l', 'f, i 101-11 4.5.1-P002-C61-R031 101-11 4.5.1 P002 821-F051C i 101-11, 4.5.1 P002 821-F0510 101-11 4.5.1 P002 821-F051G 101-11 4.5.2 P002 C61-R031 101-11 4.5 NOTE-P002 C61-R030 i (Pg. 9, after 4.5.2) 101-11 NOTE 2 P002 D23-R270 P.9(4.5)- (after p I 4.5.2) 101-11 4.6.13 MCC EF1007 E12-F0248 Compt M ] 101-11 4.6.14 Breaker E12-C0028 EH1208 l 101-11 4.6.14 P002 P45-R0338 101-11 ' 4.6.16 MCC EFID07 E12-F0048 Compt 0 101-11 4*.6.19 MCC EFID07 E12-F0038 Compt D 101-11 4.6.19 MCC EF1007 E12-F0488 [, 4 i Compt V l 101 Caution MCC EF1007 E12-F0048 Pg. 13 Compt F 1 (After j 4.6.19) [! 101-11 4.6.21 MCC EFID07 E12-F0478

i 2

1' i Compt V 101-11 4.6.24 MCC EFID07 E12-P0488 i i Compt V ,l i .i l i i i l' i !-l 1 C-3

l

)'i

M,_ r n, UN^ IES C9"TD91 '" MCI 8 ' p ' TAM A M AtY. M fx ,1 m WTMnTMM PROCEDURO STEP FANEL EQUIrrw.n t NUMBER HUMBER NUMBER NUMBER HUMAN EMCINEERING OBSERVATION I 1 101-11 4.6.25 MCC EFID07 E12-F053B Compt BB 101-11 4.6.28 EFID07 E12-F048B Compt V 101-11 4.6.28 EFID07' E12-F003B Compt D j 101-11 4.6.28 P002 C61-R025 i s RHR-A Heat exchanger inlet valve ~ control switch is a 101-11 4.3.5 P001 E12-F047A l o close-normal-open spring return when it should be a if 4 maintained switch. !~ RHR-B Heat exchanger outlet valve control switch is 101-11 4.3.6 MCC E12-F003B o EFID07 close-open switch when it should be a close-normal-Comp D open spring return to normal for a throttling valve. Procedure note should also include valve #E12-F064B. 101-11 Note Procedure o collowing 4.3.7 ll l No normal range band exists on meter for RHR A flow meter 10I-11 4.3.12 P001 C61-R005 j o IOI-11 4.3.12 P002 C61-R025 [', No throttling capability for RHR Heat exchanger outlet 101-11 4.3.12 P001 E12-F003A o 101-11 4.3.12 MCC EF10D7 E12-F003B valves as stated in procedure Comp D C-4

h DETAILEDCOTROL'ROOMDESI().VIEWFINDINGS-TASKANALYSIS y PROCEDURE STEP PANEL EQUIPMENT ) NINWI ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NIMBER .v Control range for' suppression pool temperature is not 101-11 4.3.12 P001 D23-R240 l o indicated on meter face. 101-11 4.3.12 P002 D23-R270 i l' l-NPL number is not included on label plate for control 101-11 4.4.1.2 P001' IESI-C004 o } switch 10I-11 4.4.1.3 P001 C61-R001 101-11 4.4.1.4 P001 C61-R003 101-11 4.4.1.8 P001 C61-R001-1 101-11 4.4.1.8 P001 C61-R012 l" 101-11 4.4.1.9 P001 C61-R001 l 101-11 4.4.1.10 P001 C61-R012 i 101-11 4.6.32 P001 RCIC TURB TRIP C/S i i 101-11 4.6.32 P001 E51-C004 i, o Label of valve function differs between procedure 101-11 4.4.1.6 P001 1E51-F046 { and panel (according to mimic) [ r Range of RPV water level instrumentation does not 10I-11 4.4.1.8 P001 C61-R012 ] o J include entire design specificaton range. j Design specification: down to -160" l Instrumentation: down to -150" o Awkward, non-standard'3 inch graduations on reactor 101-11 4.4.1.8 P001 C61-R012 water level recorder. 101-11 4.4.1.10 101-11 4.4.1.12 101-11 4.4.2.4 l Process units are not specified on controller tapeset. 101-11 4.4.1.9 P001 C61-R001 l o e C-5 t

h OETAILED CONTROL ROOM OESIG' g.EW FIN 0lNGS - TASK ANALYSIS PROCEDURE STEP PANEL. EQUIPMENT HUPIAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER Procedure directs operator to control RPV level 101-11 4.4.1.10 P001 C61-ROI2 between levels 4 and 7. Instrument scale is in 101-11 4.4.2.4 P001 C61-R012 o inches with no indication of level numbers. Operator 101-11 4.4.3.1 P001 C61-R012 must remember correspondence between level numbers 101-11 4.4.3.1 P001 C61-R010 101-11 4.5 NOTE P001 C61-R012 and inches. (pg. 9, following 4.5.2) inconsistent units for suppression pool level between 101-11 4.4.1.11 P001 Suppression l' pool o procedure and instrumentation temperature and level reactor (No l MPL number) CST level indication is not available at the remote 101-11

• 4.4.1.11 P001 N/A o

shutdown panel Labels on panels do not agree exactly with descriptions 101-11 4.4.1.11 P001 E51-F059 101-11 4.4.1.11 P001 E51-F022 o in procedure (per mimic) 101-11 4.4.1.11 P001 E51-F031 101-11 4.4.2.4 P001 C61-R012 101-11 4.6.30 P001 E12-F023 101-11 4.6.32 P001 E51-F045 101-11 4.6.32 P001 ' E51-F046 101-11 4.6.32 P001 E51-F059 10l*-11 4.6.32 P001 E51-F022 l Process units are not identified on the reactor water 101-11 4.4.2.4 P001 C61-R012 0 level recorder C-6 i k

.y. 'O OETaitE0CONTR0tROOMOESiiO,iEurIN0iNc5-TaSxaNatvSIS U1-PROCEDURE STEP PANEL -EQUIPMENT-4 IRfWI EMINEERING OBSERVATION NUMBER-NUMBER NUMBER 1RMBER ' o Process units are not identified on. reactor 101-11 4.5.1 P001' NUC BLR pressure recorder 101-11 4.5.2 PRESS 101-11 4.6.32 Recorder-(C61-R012) o Procedure directs use of steam tables. A copy of the 101-11 4.5.1 Procedure steam tables should be available at each Remote 101-11 4.5.2 Shutdown Panel o Poor SRV nomenclature on remote shutdown panel; manual 101-11 4.5.1 P001 B21-F051C blowdown valve does not match control room terminology P001 B21-F051D of " safety relief valve". P001 B21-F051G o Reactor Pressure Meter has unacceptable scale progression 101-11 4.5.2 P001 NUCL BLR 101-11, 4.6.32 PRESS There are 15 indices between majors. There should be les than or equal to 10.- Recorder portion of instrument has Recorder / 20 indices between majors. Meter (C61-R012) !l o Labeling of recorder / meter on remote shutdown panel is 101-11 4.5.2 P001 NUCL BLR I not consistent with terminology used in main control PRESS Recorder / room. meter (C61-R012) .b Procedure c t, C-7 i

() DETAILEDC0TROLROOMDESIf()1IEWFINDINGS-TASKANALYSIS {lll. g' PROCEDURE STEP PANEL EQUIPMENT Hum M ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER -}-i.' o Steam tables should be integrated into this procedure. 101-11 4.5.2 Procedure If supporting instructions (SVI) are required, they should be integrated into these procedures and available at the remote shutdown panels. Elapsed time can not be determined from remote shutdown 101-11 4.5.2 P002 N/A j o panel #P002. 101-11 4.6.11 i 101-11 4.6.24 o Procedure should specify reactor cooldown rate, not 101-11 NOTE 2 Procedure f just cooldown rate. Pg. 9 (4.5) after 4.5.2 i ? Suppression pool temperature trip (120'F) is not 101-11 ' NOTE 2 P001 SUPER POOL i l 0 identified by colored band or stripe on meter. Pg.9 P002 TEMP r (4.5) recorder after D23-R270 4.5.2 .I o Procedure should call out valve name as well as 101-11 CAUTION Procedure number. Pg. 13 ( After 4.6.19 l l i i } t C-8 a

e-() DETAILED CONTROL ROOM DEST ( JVIEW FINDINGS - TASK ANALYSIS PROCEDURE STEP PANEL EQUIPMENT HUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER. o Instruction could be confusing. Does it mean " turn 101-11 4.6.24 Procedure control switch to open for 10 seconds and leave in that position" or "open valve to throttling position for 10 seconds and then close?" This should be written clearer. i o Valve control is inappropriately labeled "RHR INJECTION 101-11 4.6.25 P001 E12-F053A VALVE" on current panel and " SHUTDOWN COOLING A TO FDW ~ SHUT 0FF" on new proposed design. Procedure step description should agree identically. o Wrong type of switch is installed. Throttling 101-11 4.6.28 P001 E12-F003A control not available in the current 2 position maintained contact. I o Wrong type of switch is installed. No throttling 101-11' 4.6.28 EF1007 E12-F0488 capability is available with current design. Camp V 101-11 4'.6.28 EF1007 E12-F003B Comp D l t i o There is no RPV temperature indicator at the Remote 101-11 CAUTION P001 N/A Shutdown Panel Pg. 16 P002 N/A (before 4.6.34) l 101-11 4.6.34 i: t_ C-9

T _- g, .s l s ATTACHMENT D DETAILED CONTROL ROOM DESIGN REVIEW FINDINGS TASK ANALYSIS - 501s 4 i o O

t' s Q DETAILED CONTROL ROOM DESI O /IEW FINDINGS - TASK ANALYSIS [. PROCEDURE STEP PANEL EQUIPMENT )RMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER o ' Armed' & ' disarmed' positions are not labeled S01-B21 4.2.1 P601-19B B21C-530A B21C-530B B21C-531A B21C-531B ( o Annunciator setpoint does not agree with pennissive 50I-B21 4.2.3 P601-19A R61, E9 setpoint stated in Note R61, E11 1 0 Solenoid energized lights are not a direct indication S01-B21 4.2.6 P601-19C/B B21-F041F,B i of valve position. Proposed design change will B21-F047H,0 l install pressure switches in tail-pipe to provide more B21-F041E.A { direct indication. B21-F051G,C l o ADS valves are not uniquely identified on panel nameplate 50I-B21 4.2.6 P601-19C/B Nameplate i s s o These solenoid indicators meet requirements of procedure ONI-B21-1 la P601-19C/B SRV Solenoid but are not direct valve position indicators Status Lights o Operator must determine the average of 16 temperatures ONI-821-1 Ic P883 D23-R090A,B O Poor visibility inside panel (lighting) - Operator ONI-B21-1 2 P631 Fuses must stick head in cabinet to read labels. Fuses not differentiated from other fuses. e D-1 ) l l

) DETAILED CONTROL ROOM DESIG IEW FINDINGS - TASK ANALYSIS PROCEDURE STEP PANEL EQUIPMENT - HLMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER This step should be revised to state that this 50I-B33 1 P680-4A R61-C4,C12 [ o condition is indicated by annunciators (specify) Sect.5.2 Procedure not illuminated. n Wording on annunciator legend plate is "RCIRC A(B) 501-B33 2 P680-4A R61-E5,E14 o LOW SPEED IN0P". Sect.5.2 .I o Panel meter in " RPM", procedure specifies "%" S01-B33 4b P680-4B B33-651A,B j Sect.5.2 o No identification band or color bands on meter SOI-833 4b P680-4B B33-651A,8 [ Sect.5.2 SOI-CII b3 P680-6DI, IC51-601A,B,C.D 3gangesgfneutronmongoring(SRM,IRM,APRMcovers o 10 - 10 NY) where 10 NV is greater than 100% power Step. P602 1C51-602A,B g 5.3.3 IC51-603A,B,C,D f Green rod lights for rod status will not light when 501-C11 5a P680-5C,D Full Core o SCRAM VALVES are at different positions. This will Sect.5.4 Display be hard to pick out of operable (lighted) indications. 5 and 16 o " Minimum" not defined in the procedure SOI-C34 c P680-30 C34-R614 Sect.4.1 o No units on meter scale 50I-C34 c P680-3D C34aR614 Sect.4.1 o F065A/B Center switch position labeled "STOP" should 501-C34 3 P680-3C B21-F065A,B be " NORM" Sect.4.1 D-2

) OETAILEOCOTROLROOMOESIt$/IEWFINDINGS-TASKANALYSIS I PROCEDURE STEP PANEL ESIIPMENT HlmAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER o No. process units shown on recorder scale; no MPL #; SOI-C34 4 P680-3B C34-R608 temporary labels Sect.4.1 o No process units or multiplier shown on recorder scale 50I-C34 4 P680-38 C34-R607 Sect.4.1 o Controller is scaled in 0-100 (% implied) and cannot be 50I-C34 a P680-30 C34-R614 directly correlated to RPV level Sect.4.I o No units shown on C34-R614 501-C34 a P680-3D C34-R614 Sect.4.1 o Meter on P680 has blank face. Operator must go to P601 S01-C34 NOTE P680-3B C34-R605 to read pressure Sect.4.1 l o Meters on P601 are not located in proximity to F0W SOI-C34' NOTE P601-178 B21-R6238,A I CONTROL Section of P680 Sect.4.1 P601-20B l o Meter scale should be "psig" vs. " psi" SOI-C34 1 P680-3B N27-R096A,B Sect.4.2 Awkward graduations; 30 psi intervals; 5 psi graduations 501-C34 1 P680-3B N27-R096A,8 h o Sect.4.2 ~~ j. o No scale on meter face (not suitable) 50f-C34 1 P680-3B C34-R605 [ i Sect.4.2 a I i 'c l 1 0-3

a 3 () DETAILED CONTROL ROOM DES!() 2 VIEW FINDINGS - TASK ANALYSIS g. PROCEDURE STEP PANEL. EQUIPMENT HLMAN ENGINEERING ORSERVATION NUMBER NUMBER NUMBER NUMBER o Location of Reactor Pressure meter in a grouping of 501-C34 1 P680-3B C34-R605 2 other meters for FDW A/B PRESS makes it difficult Sect.4.2 to find quickly in this procedure. o No label of units used on C34-R602. 501-C34 6 P680-3D C34-R602 Sect.4.2 o There should be a more definite indication of what RFPT S01-C34 7 N/A N/A (MFP) control is on which controller's output. Operator Sect.4.2 Op. Resp. must assume RFPT A(B) is under startup controller control 18 (Not available, not suitable) o Slowly is undefined 501-C34 9 Procedure Sect.4.2 STEP 2I o Scale is in % but not labeled as such SOI-C34 10 P680 C34-R614 Sect.4.2 OP. Resp. 26 o The operator was unclear as to the parameter by 50I-C34 10c P680-3C N27-ST3 which to verify that valve travel has stopped. Sect.4.2 OP. Resp. N27-ST4 The Red / Green lights would both be lit if the 28 valve was at an intermittent position, whether traveling or stopped. Feedback that valve is stopped would be useful. o Should provide check list of these 10 valves and 501-C34 10d their required positioning to provide the flow 4.2 OP. Resp. Procedure path. Should not rely upon operator memory in 29 verifying this flow path. D-4

F O OCTaiu0 C0a1Ra ROOM Otsict Om ria01acs - Tasx musis O: PROCEDURE STEP PANEL EQUIPMENT Ntm4N EMINEERING OBSERVATION .: NUMBER NUMBER NUMBER NUMBER L o Units not labeled on C34-614 501-C34 10e P680-30 C34-614 4.2 OP. Resp.30 o No direct indication of valve position. ' The output 501-C34 10e missing N27-F175 on the controller (614) is the closest thing, but 4.2 Op. Resp.31 valve could hang up while controller still indicates zero (manual mode). o Units on both meters should be PslG S01-C34 1 P680 N27-R191 4.3 Op.P. esp. 1 o Rx Press meter is not yet scaled (not suitable) SOI-C34 1 P680-38 C34-R605 4.3 Op. Resp.2 o " slowly" is left to operator judgement 50I-C34 4' Procedure . l 4.3 I i o No units indicated on C34-R602 S01-C34 4 P680-3D C34-R602 4.3 l' o " slowly" must be by feel of operator S01-C34 6 Procedure 4.3 } i. o Instruction directs to open N27-F175. This is 501-C34 6 Procedure l actually accomplished by using controller 4.3 C34-R614. Confusing. i t 3 I, D-5 l

i 3 7 g) I DETAILED CONTROL ROOM EESIt (,iIEW FINDINGS - TASK ANALYSIS ( PROCEDURE STEP PANEL EQUIPMENT HUMUt ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER o The C34 flow and level controllers are presently SOI-C34 4.5 P680 See j arranged on P680 in a haphazard order that does 4.5 observation not make sense to the operator (who was trained info. I on a simulator where the controllers were arranged in a different order). The controllers j should be arranged physically thus: left to right -l 1. C34-R601A C34-R601C l' C34-R601B 3 C34-R614 C34-R602 C34-R600 k I o There is presently no clear means to determine what S01-C34 3 N/A N/A pump is on the S/U controller. It is left to the 4.5 Procedure l operator to deduce by eliminating all other possibilities. o This step should not be necessary unless under SOI-C34 1 Procedure b ATWS condition; and then, PEI-1 takes precedence. 6.1 o The % units are not labeled but are assumed by SOI-C34 0 P680-3D C34-R601A,B l units. Unit progression proceeds by 5, but there 6.2 C34-R601C [ are only 3 indices between majors. Four (4) or Nine (9) are recommended. The range of these two meters is identical but SOI-C34 0 P680-3B N27-R088A,B o I. 'B' has twice the resoltuion. Operators feel 6.2 'A' has enough resolution. Therefore, consistency should be achieved by reducing resolution of 'B'. 4 i D-6

O ottaitto co"tko' aooa otsu e view ri"oiacs - Task a"a sisO...I' ~ 1' PROCEDURE STEP PANEL. EQUIPMENT HUMN ENGINEERING OBSERVATION . NUMBER NUMBER NUMBER NUMBER l

1. -

o The scales from MFP differs from RFP scales by 50I-C34 0 P680-38 N27-R078 8 an order of ten (10). They should all be 6.2 e scaled GPM x 1000 or GPM x 100. Don't mix. j o Feed pump flow meters are of a substandard size. 50I-C34 0 P680-38 N27-R078 They are too small to read accurately except j at a close viewing distance. j. o There is no feedback of pump selection, except 501-C34 1 N/A N/A switch position. It would be useful to have 6.2 Op. Resp.3 some indicator lights confirming actual selection. l o Ideally the M/A indicator lights on the controller S01-C34 2 P680-3D C34-R602 i on panel 3D should have a " push-to-test" function. 6.2 i o Deviation meter does not specify units, nor 501-C34 4 P680-3D C34-R602 I indicate range. It points to adjacent scale. 6.2 Op. Resp.2 i (notsuitable) i i o There should be a more positive indication that 50I-C34 6a P680-3D C34-R601A l the Start-Up Rx Level Controller is in control. 6.2 P680-3D C34-R601B versus the individual controller, wl.ich has the P680-30 C34-R601C l manual mode selected. 0 Slowly not defined. 501-C34 2.1 Procedure 6.3 f t D-7 i i

DETAILED CONT OL ROOM DESIL JIEW FINDINGS - TASK ANALYSIS PROCEDURE STEP PANEL EQUIPMENT tapWN ENGIIEERING WSERVATION .: NUMBER IRMBER IRMBER 1RMBER o Temporary label for Bailey Recorder. No MPL 501-C34 2.2 P680-38 Bailey number, No units 6.3 label C34-R608 o " PSI" is labeled on meters "PSIG" or " PSIA". 501-C34 7 P680-38 N27-R096A,8 This is insignificant considering graduation 6.3 Op. Resp.2&3 P680-3B N27-R191 of scale. o No face on scale of C34-R605 501-C34 7 P680-38 C34-R605 a 90-100 PSI range cannot be descriminated 6.3 Op. Resp.3 P680-3B N27-R096A,B i-on the panel meters (not suitable) N27-R191 n o RFPT RPM meter scales are scaled differently; 50I-C34 7 P680-38 N27-R411A,8 l 'A' has 200 and 'B' has 100 6.3 NOTE 2&3 o The 3800 RPM setpoint should be shown by color 501-C34 7 P680-38 N27-R411A,B I banding on the meter scale 6.3 NOTE 2&3 o Output meters are not marked as such, no labels 501-C34 1 P680-3D C34-R601A,8 l 1.3 o Indicator removed from panel, changed procedure 501-C41 1 Procedure 4.1 o What if SS is not available? Should key numbers 501-C41 2a Procedure l be identified? 4.1 I I j D-8

O OETAtiE0C0ati0ta00MOEsirO.<iEwriN0t*cs-TAs*Aaatvsisd'. PROCEDURE STEP PANEL EQUIPMENT MINlN EMllEERIE OBSERVATION .: NUMBER NUMBER NUMBER NUMBER l o There are two(2) position switches Not spring 50I-C34 2a P601-188 C41-51B loaded. 4.1 P601-19B C41-51A 50I-C41 3e P680-10A N/A Digital clock not in place yet (later) ~ 4.1 o i j o Procedure should tell how many G33 indicators 50I-C41 3f P601-188 G33 are involved and call out G33 nomenclature. 4.1 i o Orange code for " closed" is non-standard. 501-C41 3f P601-18B G33 Orange and red are not easily distinguished from 4.1 P601-188 F001 each other. P601-188 F028 P601-18B F040 P601-18B F053 i l P601-198 F004 P601-19B F034 l

i P601-19B F039 I

P601-198 F054 o No single infiication of RWCU isolation status; 501-C41 3f ', N/A N/A j must check valve positions on isolation matrix. 4.1 I i This section 5.1 is unusual in that it describes 501-C41 1 Procedure j o determining the readiness status which is not 5.1 J expicitly called for in the 501 format 0AP-0502. This section needs to be retitled, perhaps Standby Readiness verification. A section needs to be I written for the operating mode stating the parameters f to monitor by using the information in s01-C41, 4.1.3. ] o Procedure (1) reads incorrectly " momentarily" S01-C41 1 Procedure implies spring loaded switch. A two position 6.1 switch is available. l i 1 I D-9 j i

t-e.. O otrartoo coaTaot ao0M otsic Otv rtNoiacs - Tasx aaatvsis Q-PROCEDURE STEP PANEL EQUIPMENT MSMR ENGIIEERING OBSERVATION .: NUMBER NLMBER IRMBER IRMBER fl o No Nonnal Position on switch 501-C41 1 Procedure 6.1 l 3 S01-C41 2 Missing Missing o Meter 1-5x10 gallons instead of % 6.1 o Note should be reworded to state clearly if the 501-C41 3 Procedure criteria for additional injection is 6.1 a) All rods cannot be inserted or b) Reactor cannot be maintained in shutdown condition. o Procedure says " verify". Should be " actuate" 50I-C51 P680-6c Procedure I l to start. 5.1 P l' o " Desired" IRM detector is inappropriate since 50I-C51 2 Procedure all IRM detectors should be in. 5.1 I i o Operator did not verify IRM neutron flux check S01-C51 3 Procedure 5.1 i I o Procedure describes control sequence - cannot SOI-CSI Sb P680-6C N/A tell by direct indication when drive power is 5.1 l-removed. o " Deselect" action is not described in the procedure 501-C51 687 P680-6C (NT. Range nor on the control panel. The operator actually 5.1 , Monitor pushes the lit select buttons in order to Procedure }- deselect. 1 + D-10'

-2 /~ hl ( DETAILED CONTROL ROOM EES1 VIEW FINDINGS - TASK ANALYSIS _/ PROCE!"JRE STEP PANEL EQUIPMENT NUMAN ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER o Procedure says Verify should be prior to actuate SOI-CSI 1 Procedure step. Sect. 5.1 o Same POWER and DRIVE in control / indicators are SOI-C51 1.2.3 Procedure used for SRM and IRM although on panel they Sect. 5.1 appear to be for IRM only. o Testable check valve out of panel for service. 501-E12 2 P601-20C E12-F041A Control not required, only indication. 4.2 P601-17C E12-F0415 P601-17C E12-F041C o ARM and DISARM positions on collar switch S01-E12 la P601-21B E21A-S9 are not labeled. 4.3 o Collar arm switches on LPCI manual initiation 501-E12 la P601-17B E12A-S21 i switches have no indication of which position 4.3 ~, is armed or not armed. (not suitable) t o Collars on containment spray pushbutton do S01-E12 4 P601-17/20 E12-S63A.B not identify arm and not armed position. 4.6 (not suitable) o Purpose of 90 second time delay could still be S01-E12 2a P601-20B E12-S63B + accomplished if the initiation switch had a 4.6 " maintain" contact. This would alleviate the i operators from being tied up for 90 seconds holding the button. (not suitable) I t D-11

t' t: O DEmuD aNnR* = DEsu O is nN0iN0s - TaSo=usis o: PROCEDURE STEP PANEL EQUIPMENT NWWE ENGINEERING OBSERVATION .: NUMBER MMBER mMBER NUMBER o Procedure Amps specification is off by 10 x S01-E12 1 Procedure 5.2 o Non-standard meter increments (not suitable) S01-E12 1 P601-208 1E12-R100A 5.2 P601-178 IE12-R1008 P601-178 1E12-R100C o Typo in procedure IE12-F064 A(B)(C) 501-E12 3 Procedure 5.2 o The task " disarm and/or initiate" is confusing. 501-E12 1 Procedure step needs to be revised. 5.3 o NOTES in the s01 should not direct action 501-E12 9 NOTE Procedure but provide information. Rewrite as a step. 7.6 s ? o The Caution statement is in error since 501-E12 CAUTION Procedure instruction section 7.10 can be enterec 7.10 L d from Attachment I and 4 The nomenclature " contingency" does not apply to the PEI's. [ o This NOTE should be rewritten as a step since 50I-E12 NOTE Procedure J notes never direct action. 7.10 I o Scale difficult to interpret with 6 amp intervals 50!-E21 lb P601-21B 'f21-R100 4.3 [ o LPCS shutoff head pressure is closer to 500 psi 50!-E21 4 Procedure h than 295 psi as stated in procedure. 4.3 m 1 0-12 ~ l

t-O OETaltE0 CONTa0L ao0a Oest' C;1t* ria01aos - Tasx aa^tvsts ').- PROCEDURE STEP PANEL EQUIPMENT IRNWI ENGINEERING OBSERVATION . NUMBER 1RMBER NUMBER NUMBER 1 o LPCS Pump flow scale has non-standard 100's of GPM S01-E21 1 P601-21B E21-R600 5.2 1 LPCS pump pressure is not required to monitor 501-E21 2 Procedure o the system; refer to 501-E12, 5.2.1 for an 5.2 approved procedure of a similar system as well as the BWR owners Group position on NRC Regulatory Guide 1.97, Revision 2. Revise this instruction step by deleting it. (not suitable) l o Procedure specifies inappropriate valve 501-E21 3 Procedure (not suitable) 5.2 I i o Red mark on collar not obvious. Amed/ disarmed 50!-E22A 1 P601-168 E22A-52 positions not labeled. However, annunciator 4.3 alam activated in " armed" position. [ i o Ncmenclature in procedure should match panel 501-E22A 1-7 Procedure l labeling, e.g., HPCS INJECTION VALVE 4.4 i is not HPCS to CMTMT OTBD ISOL VALVE and CST is not storage tank. 3,6,9 etc., scale progressions difficult to read 501-E22A 1 Missing Missing i o 5.2 l o The instruction step should specify the MPL number 50I-E22A 2 Procedure for HPCS discharge pressure rather than the pump. 5.2 l l. i I t l i 0-13

DETAILED CON ROL ROOM DESIC IEW FINDINGS - TASK ANALYSIS PROCEDURE STEP PMEL EQUIPMENT DRDGN EMIEERIE OBSERVATION .: NUMBER NtMBER NLMBER NtMBER j, F o Inconsistent labeling between procedure and 501-E51 3-11 P601-21C E51-F013 panel. Procedure description and valve labels 4.2 E51-F046 e should agree identically. E51-F004 i: E51-F005 l-E51-F066 E51-F019 o RCIC arming collar does not have amed and 50I-E51 1 P601-218 E51-537 [ disarmed positions labeled 4.3 ,l, i t-o Labeling inconsistent between procedure and panel. 501-E51 1-8 P601-21C E51-F010 h 4.5 E51-F004 1: t E51-F005 i' i E51-F022 0 I o RCIC Pump Suction Pressure units need to be 501-E51 '3 P601-218 E51-R604 I corrected. 5.2 o RCIC TURB EXH PRESS meter is not available 50I-E51 4 P601-218 E51-R603 and not suitable. (Human Factors comment on 5.2 task analysis missing) I, o Recorder pens are not labeled 501-E51 5 P601-218 E51-C0002-1 5.2 i! l, o The controllers work differently; one is a flow 50I-G42 4 F870-28 N21-F135 fl control, one a level control. The scale on level 7.2 N21-F140 control should be in units of level, not %. The '421-R208 Pr close/open buttons on the level controller should N21-R137 relate to function. The supplemental labeling on (l the level controller stould be permanently installed. (notsuitable) I ^ D-14' l

r-DETAILED CONTROL ROOM DESi IIEW FINDINGS - TASK ANALYSIS PROCEDURE STEF PANEL EQUIPIENT NUMUt ENGINEERING OBSERVATION NUMBER NUMBER NUMBER NUMBER o The labeling of C42-F070 is inconsistent with the S01-C42 6 P870-2C C42-7070 convention used throughout the rest of the control 7.2 room. It has dark labeling on a light background, and the valve identification is in the lower right hand corner of the label instead of the lover lef t hand corner. The proper flow range (950-1000) is encompassed SOI-C42 7 P870-25 C42-R053 [' o by the smallest division on meter. The pump has 7.2 a 2000 gpa capacity which drives the range. Probably no change is warranted. o Review team note: Steps analyzed for HPCS operations SOI-C42 10 Procedure are inappropriate in this context - The HPCS SOI 7.2 (E22) does not contain a procedure which is appropriate for the support of this SOI (C42) Suppression Pool Level Meter goes from 16'2" to S01-C43 1 P883 C43-1073A/B i o 19'2". Recorder picks up total range. Both 7.1 P601-20 C43-R062A need to have scales referenced to bottom of P601-17B C43-R062B pool, rather than to 593 ft. o No isolation valve status is shown in the S01-N21 NOTE N/A N/A control room. Possibly ERIS 4.1 t o No units labeled on controller S01-N21 1 P650-2D N21-R475 4.1 4 D-15

p DETAILEDCONTROLROOMDESIGO,itPiNo1N05-TASxANatvSis d-. t-PROCEDURE STEP PANEL EQUIPMENT M ENGIIEERING OBSERVATION 11 UMBER IRMBER NtMBER NtMBER i No direct indication of the flow control valve. 50I-N21 1 N/A N/A o Operation is verified by looking at condensate flow. 4.1 o No units specified on M21-R323 501-N21 2 P680-20 N21-R323 4.1 No unit or parameter labels on controller scales 501-N21 3 P680-20 N21-R247 o 4.1 Operator cannot directly read GPMs on the controller 501-N21 3 P680-20 M21-R247 o tapeset or the recorder. This requires conversion 4.1 factors. (Not suitable) o Label is psi; should be psig 50I-N21 5 P680-28 N21-R276 4.1 A.B.C.D Indications are in % instead of GPM on the 50I-N21 1 P680-20 N21-R475 controller. No units or parameters labeled 4.2 N21-R323 o N21-R247 on controller. (not suitable) o Range not given. Units not given and not 50!-N21 2 P680-2C N21-R475 on the controller 4.2 o Units not labeled on level recorder 50!-N21 2 P680-2C

• $21-R323 4.2 D-16 ~

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DETAILED ROOM DESI. t!EW FINDINGS - TASK ANALYSIS i IWGN EMtIEERIM WSERTATION 11UIBER 1RMBER IRMBER. EQUIPIENT PMCEDURE STEP PANEL 1RMBER o No units or parameter labeled on controller 501-N21 1 P680-2c N21-R475 4.3 j I o " Reasonable" deviation not defined ~ S01-N21 1 Procedure 4.3 o Units should be "PSIG" vs. " PSI" on meters 501-N27 3 P680-38 N27-R046 l 4.2 1 o No scale on meter (not suitable) 501-N27 5 P680-3c C34-R605 4.2 h !i No units or scale sulgiplier on recorder scale 501-N27 6 P680-38 C34-R607 ? o (should be Ib/hr x 10 ) (not suitable) 4.2 o Units on indicator and as listed in procedure are 501-M27 6 Procedure i different (Ib/hr, gpe) 4.2 l o No labels on M27-R080. No units 50!-N27 1 P680-30 N27-R080 4.4 l' t N27:F010 o Temporary nameplate 50I-N27 1 P680-3C 4.4 o Procedure should call out FII0 as well as F010 501-N27 1 Procedure i 4.4 i 9 6 D-17

F i. O OcTAitto CONTa0t R00a Ocs'<r Otv riaDiacs - Tast aaa sis t: I PROCEDURE STEP PANEL EtWIPMENT IWWI EMIMERIM RSERVRTim

NtfSER 1RfGER NIMBER 1RfGER Process units not on meter scale (%)

501-N27 IK P680-3C C34-R602 o 4.4 No unit or parameter labels on N27-R090A(8) 50!-N27 10 P680-30 N27-R090A,8 o Recirc Flow Control tapeset and output meter 4.6 I L o The RFPT A(B) manual speed controls do not have 501-N27 11 Procedure i a mechanical stop at t5e "0" position. 4.6 i Instruction needs to be rewritten to delete this subtask (Not available, not suitable) o Process unit disparity (not suitable) SOI-N27 13a P680-38 M21-R051 I 4.6 N21-R111 o Process unit disparity between plant edict that 501-N27 13c P870-78 N33-R181 all vacuums be in inches Hg. No disparity 4.6 Procedure 'i. l-between procedure and panel meter currently. F Since this pertains to equipeent safety, a CAUTION 501-N27 14 Procedure o statement would be appropriate 4.6 o Instruction should specify that the RFPT HP S01-N27 14 Procedure and tP stop valve position indication is on 4.6 j P870. [ o ARB reters have different scaling 501-N27 14K P680-38 N27-R411A,8 4.6 i l i i l l i D-18' fl

~ b-DETAILED CONTROL ROOM DESIL CVIEW FINDINGS - TASK ANALYSIS O: ~ PROCEDURE STEP PANEL .EQUIPfENT 18f441 EMIIEERIE WSERVAi10N .:NUPRER 1RMBER IRMBER 1RNBER o Spring loaded valves need indication as to 501-N27 a P680-3c Generic whether they are throttle or not 4.10 o This valve has a tee;:orary label, which does 501-N27 b P680-3c N27-F150 not agree with other control room conventions 4.10 o Temporary label SOI-N27 5 P680-3c B21-F065A,8 4.10 o Wording of procedure is poor regarding 50I-N27 NOTE Procedure significance of reactor being critical. 6.2 Perhaps " Reactor Power above (some level)" would be more useful to operators. P680-3C N27-F010 o Operator was unclear as to why there were two SOI-N27 2.- sets of indicator lights for this. F110 has a 6.3 N27-F110 temporary label and was not on the simulator. He thought one might be a low flow indicator. It was confirmed that these were two different sized valves. Both should be green. o Step 6.3.4.b. is incorrect. The F170 valve 50I-M27 4b Procedure cannot be closed in this manner. It must be 6.3 closed by the F170 switch. The flow controller will not close it after the MFP has stopped. o The F170 switch is only energized if the MFP 501-N27 48 P680 N27-F170 breaker is open. It would be helpful to 6.3 have an indication of this state. D-19

~ DevriaotasS-TASxA#atvSrS O i. O ~ ot'^co co Tao' aoo" otSi 4 q PROCE00RE STEP PANEL EQUIPft:NT ^ IRMAN ENGINEERIE OBSERVATION . NUMBER NUMBER 1RMBER BRMBER o Wording in procedure should be identical to 501-N27 5 Procedure i labeling nomenclature used on the panel. o MFP tameter noted as not suitable (no explanation 50!-N27 5 P680-38 N27-R295 on task analysis sheet). 6.3 t o Procedure says decrease speed to 20% RPM. This 50I-N27 4 P680-38 N27-R411A,8 should be specified as a number. It's presumed 6.4 to be 20% of rated RPM or 1100. 4 o Indication of 7,000 GPM critical flow on meter 501-N27 5 P680-38 N27-R088A,8 would be helpful. 6.4 o Abbreviations in procedure are different than 501-N2/ 6 Procedure { l label 6.4 + i o Manual speed control of RFP B does not have 50I-N27 8 i P680-3C N27-R425A,8 mechanical stop. The control for RFP A, and 6.4 j those in control room #2, do. There should be j stops on RFP B control. 1 I [' j o HP/LP Stop Valve positions are not labeled as 50I-M27 9 P870-8C N27-526 i 4 such. They are located above test switches. 6.4 N27-527 ] Label should be changed. N27-530 i l N27-531 1, j o A pst graduation scale on ptnrp discharge 501-P42 1 Missing Missing pressure meter is awkward. 4.2 f o P45-R602A(B) should read E12-R602A(B) 50!-P45 2c Procedure j 4.3 1 ^ l ) D-20 l

j .;O ~ *. ATTACHMENT E . DETAILED CONTROL ROOM DESIGN REVIEW FINDINGS OPERATOR EXPERIENCE REVIEW BY J.L. SEMINARA

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1.0 INTRODUCTION

During the Fall of 1981 a BWROG survey team conducted Perry Plant operator interviews, to take advantage of operator experience in conducting a human factors review of unit #1 and #2 control rooms. The results of these interviews were summarized in a report entitled: " Human Factors Design Review of the Perry Control Room" which was completed in early 1982. During the week of June 11-15, 1984 another series of interviews was conducted to obtain an operating experience update based on the training and experience accumulated during the intervening years. A questionnaire was developed and distributed to approximately fifty operational personnel with a wide range of experience extending from Reactor Operator license condidates to shift supervisors. Beyond the questionnaire data received from 43 respondents, twenty interviews were conducted to discuss and amplify' the questionnaire responses. b These interviews were conducted on an individual and private basis ~ with interviews averageing approximately one hour in length. In selecting interviewees, preference was given to those who had received license training.

The questionnaires and subsequent interviews were divided into two k

major, categories.of questions: Part I dealt with procedures 'and Part p 'II covered control room design issues. Appendix A provides a copy of L> the questionnaire. Human factor concerns raised during the interviews;were photodocumented where possible. ^, ~ E-1 m 7 w-,y- ,--y- ,,n --y--m-w-m,gwy.my,,.,,,- gyg 5,wgr yww w wg, w.9 77 m +4,wb"NNW 9 74 WMW W W--S't we -F -+Ww"f'-"*f*' +- '""e- * " " ' " " "

. -....=--- -. N ~ A>-------....~..--.. .t 2.0 OVESTIONNAIRE/ INTERVIEW SAMPLE ) \\. Auto-biographical data from the questionnaire is summarized below: Job Position Whole Sample Intirviews Shift Supervisors 5 2 Unit Supervisors 8 4 Station Operators 23 11 Others: Operations Engr. 7 3 trainers, Reactor Engr. Totals 43 20 Years Experience (Averages For Whole Sample) Commerical Navy Fossil Nuclear Nuclear ( ) Shift Supervisors 1.6 yrs 5.4 yrs 0.2 yrs Unit Supervisors 2.2 yrs 4.6 yrs 4.3 yrs Station Operators 1.9 yrs 5.7 yrs 0.8 yrs ~ ~ Others 1.8 yrs 2.6 yrs 0.1 yrs l The ' sample is largely composed of personnel with Nuclear Navy experience. All five shift supervisors are ex-Navy personnel. Five unit supervisors are ex-Navy while three have a fossil plant background. Twenty-one out of twenty-three station operators have Navy experience with only two from the fossil plants. i d l A,) - E-2 -,-aew -pn~wmm-<.w=-e, -.,-.c - +, -. - c-

G._, ._~ ,]. Educational Background (Highest Level For Whole Sample) ,1 - b.. ' AA or 2 yrs HS College BS. Shift Supervisors ' 2 3 0 Unit Supervisors 4 3 1 Station Operators 17 6 0 Others 0 2 5 Totals 23 14 6 Age'(Averages For Whole Sample) Shift Supervisors 34.4 Years Unit Supervisors 33.0 Q~ . Station Operators 29.7 I (. Attended License Training (Whole Sample) Whole Sample Interviewees Yes No Yes No Shift Supervisors 3 2 2 0 Unit Supervisors 7 1 4 0 Station Operators 11 12 8 3 L Others 3 4. 3 0 t l . Totals 24 '19 17 3 (O) E-3

....L, c,l==, n.- ,. G L., D:.. ..es: 4 sn.^. -:T~ e.......--. 4 Ih 3.0 QUESTIONNAIRE - INTERVIEW FINDINGS ) i The ensueing paragraphs sumarize the responses of the questionnaire / interview sample to,each question posed in the questionnaire fonn .provided as Appendix A. The number in parethesis following each paragraph heading is the item number from the questionnaire (AttachmentA). Although forty-three individuals responded, a number of questions could not be answered by some due to a lack of experience or training on some of the specific issues addressed. For each question between 18 to 32 participants responded in this survey. The total number that comented on a given question is noted bets in conjunction with each topic heading. The' notation"(N=22)",for example, signifies that twenty-two out of forty-three people who participated in this survey offered a response to the specific questior. raised. Figure 1 provides the layout of the unit il control f room. O, .f i 3.1 ATTITUDES TOWARD PROCEDURES 3.1.1. STORAGE LOCATION g PLANT EMERGENCY INSTRUCTIONS (PEIs) (I.A.1) (N=12) Most of the survey participants did not have any opinions regarding the storage location of PEIs in the control room. Several reasons were given for this: uncertainties regarding the final layout of work. stations and lack of experience in the control room with PEIs. The PEls and other procedural documents are presently stored in or atop bookcases that flank panel P805 as shown in Figure 2. Eight. members of the sample saw.no change needed from the present arrangement.. Four respondents suggested the following changes: (1)a procedures rack located on top of P805 in addition to the.two. present bookcases and -(2) distinctively colored PEI three-ring binders so - that they are easier to pick out and lay down open. Two cautioned h) G E-4

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. = _ that any rearrangement of the work stations should ensure that procedunes were stored within the confines 7fte%o'sesho'e to avoid- -- ---~ ~ r operator absence from the center of activity. 3.1.2 PROCEDURELAYDOWNSPACE(I.A.2)(N=18) Only 18 respondents ventured an opinion on the adequacy of laydown space. Thirteen members of the sample indicated that they had no experience or knowledge on this topic or were unsure of the final configuration since the layout of workstations is still evolving. Of the eighteen who did respond, a minority of seven indicated that no change was needed. The majority of eleven felt that laydown space was inadequate. The horseshoe was described a's cluttered. TheP805 shelf (SeeFigure

3) was felt by some to be insufficient for laying down surveillance procedures, operating procedures, prints, coffee cups, etc. At present the sloping back of P805 (See Figure 4) is used as laydown space. Several respondents expressed the need for movable stands for procedures so that an operator could refer to them while manipulating controls. At present, wooden stands are appended to the rail along the front edge of P870 and P601/877 as shown in Figure 5.

L-Suggestions offered for augmenting procedure laydown space were: (1) A fold-out or fold-down extension to the writing shelf on P805; (2) A laydown shelf attached to the back of the center pillar; (3) A centrally placed table behind the pillar to spread out PEIs based on l theemergencydrillexperienceand;(4)Foldablemusicstands. One i l unit supervisor comented that sufficient laydown space was available at his station. { g,7 m w wm-r

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{Ie -( - - 3.1.3 PEI FORMAT AND PAGE LAYOUT-(I.A;3)(N=26) ~ ' ~ The majority (20) were highly critical of the present format and page layout. Only six of the respondents saw no need to modify the format of PEIs. Coments made were: o Steps should be fully numbered, e.g., 5.2.3.6, rather than just the last digit, for ease of reference from one section to another. o Flow charts (see Figure 6) are needed to provide an overview of events PEIs are difficult to follow. o Contingency steps provide a confusion factor or time delay that is unnecessary in some cases, r N). o Capitalize key words and be as concise as possible. Avoid i phrases such as "in accordance with" and "as applicable", o Need separate tabs for each attachment to PEI-1. The shift supervisor will be going through the PEIs and he o can be in 5 or 6 places at once. Add tabs and improve ~ formatting or it is easy to get lost. ~ o Start a new page with each section, e.g., 3.1, 3.2, etc. Section 3.2 presently starts at the bottom of the page where it is hard to find. o Provide concise list of actions rather than wordy paragraph instructions, e.g., paragraph 3.3.7. 3 E-11 .. - - ~

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.'.._^ 1 20 r. o If you are'ln oE'bTffereritproceduresato'nc'e,youwon't ~ have time to pay attention to the instrumentation. - o Duplicate steps rather than flip back and forth to different sections. o PEIs are far too complicated to follow under stressful situations. Its hard to know where to go next. How can someone with 30 seconds start to follow the book? I 3.1.4. CAUTIONSANDNOTES(I.A.4)(N=24) Of the twenty-four respondents to this question, twenty felt that 4 cautions and notes were adequate and recomended no changes. A small minority of four respondents expressed the following concerns: (1) h-Notes and cautions may get lost..They may need to be highlighted, a j . e.g., yellowing. (2)Somenotesandcautionsareunnecessary considering the fact that a PEI is being used, e.g., cooldown rate may be exceeded if.... (3) Notes and cautions may interfere with 4 - action steps. (4)Somenotesorcautionscontainactionstepsthat might be missed under stress. - 3.1.5. TRAINING (N=27) The general consensus (23) of respondents who had received training in the use of PEIs was that training was not sufficient. As one put it: " PEIs are very detailed and complex procedures with concurrent paths which must be followed. Training was too short. Frequent exposure to PEIs is necessary with quality training to give an in-depth knowledge to those who must use them if they are to be O ar as v 1a ia a ccid at

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0 3 t The operator sample was concerned more witt the brevity of training and the. learning decay.over. time rather_than the quality of training received. Several took pains to note that simulator training was excellent and that the instructor (Stratman) was highly competent. ~ One recommended the need for more simulator time using PEIs with realistic shift manning. Another felt that training was required regarding the bases for PEIs and their objectives. One respondent summarized the general attitude of the entire sample: "We need more training... I don't feel comfortable yet with the PEls." A training instructor recomended at least two days of classroom training dedicated to PEIs followed with a minimum of three days in the simulator for R0s and SR0s during initial certification. Subsequently there could be 2-3 days for refresher training during license class. O 3.1.6. PEI LEVEL OF DETAIL (I.A.6)(N=24) Most people responding to this question (15) felt that the level of detail for the PEls was proper. Minoritysentiment(9)wasdivided between those who felt that too much detail had been provided and those who perceived a lack of detail or omissions. An example of insufficient detail is: " Include overview of off-site dose calculation methods and raise the level of detail in general." One who felt that detail was excessive gave the following example: 1 "The PEls are too wordy. This causes slow reading. There are six or seven sentences to say a simple thing. For example, Page 3 of PEI-1, paragraph 9.b.2 reads: Ov E-14 ' ~) ~

~.- a {O - ei .2) Fbr th65e 'listems'11sted below'wh'ii:h';" ~~ --' '" ' "~ ~ '--' are not operating, depress the associated divisional manual initiation .pushbutton and immediately override the associated injection valve to the shut position. LPCS LPCI-A LPCI-B LPCI-C "This paragraph could simply state: Initiate and override: 0-LPCS LPCI-A LPCI-B LPCI-C 3.1.7. SUPPORTING CHARTS AND GRAPHS (I.A.7)(N=24) Of twentf-four individuals responding to this question, seven saw no .need for change. The majority (17) reconnended one change or another. The most frequent suggestion favored the inclusion _of flow charts, mentioned earlier above, to provide an overview of PEI events. As one put it: p O' E-15 %) L h

.( n "Many operators have. a great, deal.,of difficulty getting a_ grasp on PEIs because they are confusing. Part of this confusion is eliminated by use of a "roadmap' or flow diagram. I think it may be worth considering including flow diagrams in the PEls." Another suggested that the flow charts should be enlarged and placed under plexiglass, thereby, allowing the user to mark the path beiig 4' followed and obtain an overview of past events and future directions. Other suggestions pertaining to charts and graphs were: (1) Provide detachablecharts;(2)Laminatechartsandgraphs;(3)Repeatcharts and graphs near the steps where they apply to minimize search time; (4)ProvidechartsandgraphsthatcorrespondwithERISdisplays; (5)ProvidechartandgraphdatapresentlyinthePEIsc.scomputer + displays and (6) Clarify the confusing 3-axes chart in Attachment 1 of PEI-2. l'3. 3.1.8. PEIENTRYANDEXITCONDITIONS(I.A.8)(N=21) The respondents were about evenly divided between those (10) who sa'w noproblemswithENTRY/EXITconditionsandthose(11)whofoundthem troublesome. Some found the exit conditions more confusing than i~ entry conditions: Its hard to get out and feel good about it since L~ exit conditions are vague." Another pointed cut that-alarms did not A t'ird viewpoint expressed was that h correspond to entry conditions. " entry is too easy... the PEIs should be used as a last resort." One i. respondent suggested that entry / exit conditions be memorized, thereby . simplifying the PEIs. i l E-16 i Y we +w ya+.-,w-w-e

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- ~ n -. -.. ~ 4 A 3 ( (., - 3.~1.9. 'USE OF MANUAL OVERRIDES (I.A.9)(N=19) ~- The majority of respondents (13) were satisfied with present manual i override pro::edures. Only six respondents expressed reservations and -recomendations which are illustrated in Figures 7 to 11.

3.1.10. LACK OF INFORMATION OR CONTROLS NEEDED TO CARRY OUT PEIs (I.B)(N=29) t The majority of respondents (16) did not see a need for additional information or controls to carry out actions required by the PEIs.

Thirteen respondents perceived a need for the following improvements: -(1) Improve labeling of terminal points for fuses in back panels, (2) Color code fuses and terminal points referred to in PEIs, (3) Provide MSIV _ tailpipe temperature indication, (4) Clarify Tech Spec limits, O cs)eEIandmeterdess9nationsshouidmatch,aed(6)PEI-1caiisout " adequate core cooling". What is adequate and how do we determine this with cur instrumentation? 3.1.11. RECORDERS OR INDICATORS THAT ARE DIFFICULT TO SEE DURING EMERGENCY OPERATION (I.C)(N=31) About one-third of the respondents (11) reported no difficulties with visual access to displays'during emergencies. Themajority(20) expressed a variety of concerns. The most comon complaint related to the mass of miniaturized, difficult to read displays located on .P-680(SeeFigure12). Missinginformationincludes:-(1)1 rend informationonthemainsteamlineradiationmonitors.(2) indication D of instrument power AC or DC for displays, and (3) out-of-sight information on backpanels, e.g., radiation monitors. o v E-17 o a, ~ ~ E- ..,,.--.a._._-_._.---.-,_._.-._...--,.,_..._._..-..-.---.-.,.-..,.,,,-....---

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~ (, .=..:...... a : ....... _. a..~ "p, ' 9% a } kh -' b T i h a 4 r T j l ll [ 9g ) h I l l 4 r 3 j i I>h j I J + ) i 3 l -kinby.1 i W l i O ~ = - -. .E'l:- ' M2hl! $ yll' h ; r M fi _ey: j '!J h A En ed, t r j l ED l' E3 l EM I l d l E3 i 9 l 151 <a gm -l;) k B^ a k. i h < A l -Yg: Figure 10. Fuses in some backrack' panels have label plates that are on holders which rotate and expose fuse identification markings. l i These movable label plates were recomended for cabinets where L manual overrides are required. 12 95 e

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~,;.. .? Complaints were also voiced regarding smoked glass recorder windows (e.g.,RHRTEMPE12-R601),narrowrecorderswithpensonthe right-hand side where innediate trends are not apparent, and the support column in the center of the horseshoe that blocks visibility of indications (See Figure 13). 3.1.12 ERRORS OR INCIDENTS THAT COULD HAVE BEEN AVERTED THROUGH IMPROVED PROCEDURES (I.D)(N=20) Those who responded to this question were evenly divided (ten respondents in each category) between those who attributed errors or incidents to procedures and those who did not make this association. The causes mentioned were repititions of earlier comments: deficient PEI format, problems with entries and exits, and keeping one's place Q-in the PEI. ,f 3.1.13. PROBLEMS USING OR UNDERSTANDING PEls (I.E)(N=31) I i The overwhelming majority of respondents (27) had experienced problems using or understanding PEIs. Only four stated no problems. The problems identified were a composite of difficulties mentioned in response,to'other questions in this questionnaire: (1)flippingpages backandforth,(2)branchingofPEls,(3)insufficienttrainingand (4) overly-wordy PEIs. 3.1.14. PARTICULARLY DIFFICULT OR CONFUSING PEls (I.F)(N=25) Theoverwhelmingmajority(23)reporteddifficultieswithPEls. There was general agreement that PEI-1 was especially difficult and (] ') E-24 t

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.m mum g s yvs tm .n n 4 -m. 2-r. . !u gM' ,~ ww,mg.. u- $- 1 4 ?O $.,.. - JWj gg. - e- -- N0 TOUR WE gpg Access igna NO TOUR 7W Mu ACCESS - w -y.wQ Q !.g d ADMrne ..... ; 2:- M [' -s i 1.. U p. p'9L., f*=':5 . ? S-? 9 f ~ ^ 965. if4.: +.. k:h3: . -.'v= ~ *- y C ~.. n. O Figure 13. The centrally placed support column blocks visibility of indications. This view from the U.S. station also illustrates ..l that the operator cannot be seen when he is stationed at P-680 or P-805. E-25

i + .. :. ~ ( c.... :. te..... confusing. Several also singled out attachment 5 to PEI-1.as troublesome. Five respondents felt that all PEIs were confusing in general. Only two respondents felt that the PEIs were not difficult on confusing. One; interviewee remarked that PEI-7 is so general as to be worthless. VAGUE OR GENERALIZED STEPS (I.G)(N=24) 3.1.15. R Themajorityofrespondents(15)didnotfindstepsinthePEIsvague or overgeneralize'd. Aminority(9)notedthefollowingproblems: (1) Notesaregeneralizedandnotreallyunnecessary;(2)PEls2and3do not give instructions on what to do if NCC can't be restored to the Containment /Drywell; (3) PEI-7 is vague; (4) PEI-1, attachment 1, step 3tableisveryconfusing;(5)Toomuchdetailisprovided,and j -(6)Notclearhowtoventcontainment. O-3.1.16. NECESSITY FOR REFERRING H OTHER PROCEDURES (I.H)(N=25) The twenty-five responses to this question were fairly evenly divided regarding the necessity to refer to other procedures in order to 4 carry out the actions required by a PEI. Thirteen indicated no need to refer to other procedures. Twelve respondents indicated a need to refer to other procedures in executing PEIs, but this was not f perceived as a major problem. 3.1.17. USELESS STEPS IN,PEls (I.I)(N=22) Of the 22 responses to this question,18 felt that'the PEls were ' devoid of useless,or nonessential steps. Only four respondents disagreed. One noted that PEI-7 in its entirety was " useless". - Another felt that portions of-PEI-1, e.g., " Monitor and Control . Reactor Power", are worthless. O E-26

(, ,. 2.'... _....- -. 3. hi 8. NECESSITY T0-MOVE-AW'AY; FROFREtATED CON'TROLS T0 HEAD'AM"-' INDICATOR (I.J)(N=25) Fifteen out of twertty-five responses indicated a necessity to move away from related controls to read an indicator to verify that an operator action had the desired effect. Ten respondents reported no such need. One unit supervisor did not see a problem in this area with the availability of ERIS. Some examples of dissociated controls and displays noted were: (1)WeneedaReactorPressureindication near the Main Steam Line Safety Relief Valves. (2) The CST Level is onP870acrossfromHPCSandRCIC(P601)whererelatedcontrolsare. (3) There are no RPV Level instruments that can be read from the HPCS orRCICcontrolarea.(4)Indicationsarespreadout-especially RCIC and HPCS on small break LOCAs. 3.1.19. SUFFICIENCY OF TRAINING (I.K)(N=32) (Q ,.J, The majority (25) did not feel sufficiently trained to carry out all actions required by the PEls. Only seven respondents indicated that training was sufficient but with the qualification that periodic retraining is necessary. ~ 3.2 CONTROL ROOM ISSUES 3.2.1. ADEQUACY OF SHIFT COVERAGE (II.A.1)(N=26) The majority of respondents (15) were satisfied with present or anticipated shift coverage. Theminority(11)expressedseveral concerns regarding manning, shift composition, and shift rotation practices. Increased manning was seen as a need due to fire brigade duties and other emergencies that would take the unit supervisor or E-27

tO y ..... plant operators away1 rom # heir nomai duties.-" Sample recomenda ~ ' - --- ~ " * '-" t t_........-.. tions made were: (1) provide two unit supervisors per shift; (2) provide additional auxiliary operators if they are going to be involvedinthefirebrigadeoremergencymaintenance;(3)providea shift supervisor available around the clock, a clerk on afternoons and two 50s per shift; (4) It would be preferable to have permanent shifts (one to one and one-half months duration) for midnight shift; (5) more time needed for turnover, and (6) Need a lead auxiliary operator. 3.2.2. CONTROLROOMACCESS(II.A.2)(N=23) Most respondents (19) saw no problems with control room access. While access might be liberal at the present time, it was anticipated that it would be adequately controlled after construction and checkout activities ceased. The minority (4) raised several issues regarding access: (1) There should be a second way out of the control room for emergency escape. (2) Access to the control room should be controlled by the 50 rather than the unit supervisor. t 3.2.3. CONTROLPANELLAYOUT(II.A.3)(N=25) The majority (17) of respondents were satisfied with the layout of control p'anels or offered no recommendations for change. ~Approximatelyone-third (8)oftherespondentsmadecomments regarding the cluttered horseshoe area (See Figure 14), the center support column, the overly-small P680 meters, lack of grouping of level controls and PEI entry conditions. Itwasalsosuggestedthatmimicscouldbeimprovedby(1) establishingcolorcodingconventions,(2)relatingmimicsto l associateddisplaysand(3)showingimportant,interconnectionson l-all mimics. 1 E-28 l

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i ..? .. -_3,_g,-4;.--60MMUNICATIONS - '(W.-Ad-)$=26F--- ' -- - - C-- ? s..... Slightly more than half the respondents (14) expressed difficulties with the comunication system in the control room. A major complaint had to do with the heavy use of the five-channel page system by construction workers during day shift limiting its usefulness for operations. Control room operators are constantly exposed to irrelevent page messages. One suggested a dual paging system. Another would'like to find a means to detect individuals who abuse the page and introduce needless distractions all day long. A second category of complaints dealt with the unreliability of the communications system. As one put it: "The present five line page system does not work most of the time and is totally inadequate." Several stated that they were having difficulty reaching Plant Operators in various areas of the plant. The need was seen for more 3 phones throughout the plant, more headphone jacks, and an improved ,f plant radio system and walky-talkies. Several floors of the turbine building and the high radiation area were singled out as offering difficulities in reaching people. i One' respondent felt the need for a PA phone on P680 and at the end of P870. Another suggested a phone / intercom to the area immediately ~ ~~ outside t'he control room where auxiliary operators are generally located. 3.2.5 INFORMATION FLOW (II.A.5)(N=22) -This question did not elicit much response from either the . questionnaires or the' interviews. Eighteen (18)indicatedthatno-change was.needed. Only four members of the sample had coments to offer: One felt that the' shift supervisor's office should straddle =the doorway between unit 1 and 2 control rooms so that the shift .O.- u-.

d i __.. s.upe,rvisor, can view both_,_oRera,tjonal areas _ (See Figure l.5)._Another_ remarked that there appears to be little information from Chemistry -and Maintenance departments to the control room. One interview expressed the need for more official memos. 3.2.6. FURNITUREOREQUIPMENT(II.A.6)(N=21) While eight respondents saw no change needed in the arrangement of furniture or equipment, thirteen made suggestions for modifications: -(1) location of the shift supervisor's office in the control room; (2) More space in the overcrowded horseshoe area; (3) smaller desk at the operator station in front of P680; (4) reduce the size of the column; (5) place the ERIS console on the unit supervisor desk closer tothehorseshoe(SeeFigure16);(6)moredeskspaceforspreading outprocedures;(7)providestorageat50sdeskand(8) provide coffee pot and pemanent floor plates in the control room. 3.2.7. CCMpVTERS (II.A.7)(N=24) .Three-quarterso_ftherespondents(18)feltthatnochangewasneeded with respect to computers available to operators in the control room. However, several indicated the need for training in the use of printers and both training and operational procedures for ERIS and the process computer. Two respondents suggested that the ERIS function keys should be identified with verbal descriptors rather-I than numbers.. Some concern was also expressed.that the PC keyboard is.vulnerabletocigaretteashesandspilledcoffee(seeFigure17). Three responses dealt with the location _ of the ERIS CRTs. One felt, as noted earlier, that the ERIS CRT at the unit supervisor desk would be more useful in the horseshoe since the unit supervisor will want to be closer to the action in the horseshoe in an emergency. Also, the. unit supervisor will want to keep track of control board j. parameters without having to depend on the operator. L i E-31 E l E

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/~N, U ..... ~. - 5 4g.- ;S L: f~ " 3 29 P-- - nu .p . Ir ,F- .V re p; 't y4 -g .. s . _) g g-A *t Y A+ gr4r._ s. ~ 4 =' 4-3 g y _r .s. i;. -,.. p -- - kp+fh '"., Os0 ) _6$$ ' ' ' g--; s,s. p' O 5 %en aw= J 'W .. - '.;r.,.. .s 5-: m ~. : g . {p l N @Q b Ys h, frce

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~ Figure 16. An ERIS console has been made available at the U.S. station. Some feel that this console should be closer to the horse-shoe. /~h V E-33 .. ~. -

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= t m a : :qy a ra.-_. r:-~t_ _~-J-;~w~--1 h@ .:ll; h: Y. i 1 4-4 e s, -.; .......--..r, . g;.. ...... m m m. g:s .-4 ..;.i;q; +r. mm e- ..Lic :, O ) should Figure 17. It was suggested that the ERIS function keys (top photo)d replace numbers with verbal descriptors. The PC keyboar (lower photo) appears vulnerable to spilled coffee.

.~ .= s ~ Another. felt that it was awkward to use the PC screens on P805 in ,i,.

enjunc44on-with the P680-consolehfigure4B) --ThGii.ita LC constantly look back and forth between the two opposing consoles.

This operator felt that the PC screen should be on P680 since the ERIS will not be us,ed on a day-to-day basis whereas the PC displays are used constantly _ in conjunction with P680 functions. The third response on this topic suggested that the ERIS CRT should be-located so that it was within view from the P601 and P680 consoles. 3.2.8 MISCELLANEOUS CONTROL ROOM FACTORS (II.A.8)(N=6) When invited to comment on other control room factors not covered by the foregoing questions, six respondents took the opportunity to l mention the following problems: (1)Removethesupportbeamfromthe control room or make it as small as possible. (2) Annunciator alarms } i should not be so loud and obnoxious. (3)P671,P672,P670andP669 are not logically related. -3.2.9. CONTROLSTHATAREDIFFICULTTOOPERATE-(II.8)(N=25) Most respondents.(14) were satisfied with the operability of ~. controls. A minority (11) had the following specific complaints regarding controls that are difficult to operate: (1) controls that are spring-loaded and are hard on the thumbs; (2) inability to l distinguishbetweenastrokevalveandathrottlevalve;(3) feedwater system controls are elaborate and difficult to operate; (4) The C91 terminal at P805 gets stuck frequently because it doesn't fit i- [ quite right; (5) The CNDS FILTER BYPASS control options are l .CLOSE/0 PEN while the DEMIN BYPASS control options are oriented, OPEN/CLOSEand(6) Some pushbutton controls look identical to indicator lights. (See ' Figure 19). i E-35 I p

h. 1 / ~ ~ 1.... gem _m ' ;. 'e manggrpmca ~~ MS M.S[*= W '-~TFW = = sii ~ P' gl k "~ l " ~ q -l e d4.. ) ,y T p cc $_.v.w= ud :-;,,,_ ^-Q -l=~ ^ u_-m ~. --_ __ _ %dhi$$DD$hE.N5F.2'k h \\ r=- m a _ __ _ %m=**W ~~ WW~"3i O ~ y l:. 'p {j} 1 l x. ' st m i i ~ $'$ .;l s .: c. ,, h-. .A. y.dt f Qa a <.n& g -{p s bh }3 ~ 7, - a ith ? .Q-k.7 As / ar- ..m.. _h e&py, z.~%fff = -,1 .h -n b t n ry w e- .a m 'QT b ,jkh ~' .p t .e $.,, w.j.. e..m--:-- os s, g' el 1I n

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.n a x....fm a O Figure 18. ERIS displays have been placed on P680 (top photo) where the PC CRTs used to be. The PC screens are now located on P805 l (see lower photo) opposite the P680 console. E-36

0, 1 gtur#"9^- .,,s. I,P, ' "T40 =E ^ ul!FRlBW9'dd- '. T ma s > $ps.. y -pgaarame.w " JL i p U'O45FM Nd il. @,. ven.asu waga,,- P', __.= - m i b; [_ " YE. h-g e !.1= 44 An fiiTIS

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.x. w.. : 6(,. 3.2.10. CONFUSING RECORDERS OR INDICATORS (II.C)(N=29) .The great majority of respondents (24) voiced complaints on this topic. Only five respondents saw no changes needed. Four respondents made no specific coments since current problems with recorders or indicators were reported earlier and are scheduled for correction. Five complained of the disparity in units for vacuum gauges - inches of mercury vs. psig. Sometimes recorders and meters

are in different units. Four operators complained about the mini-meters on P680 which, as noted in response to other questions, are too small for quick and accurate responses. Three operators were dissatisfied with the narrow Bailey recorders that write "around the corner" and do not show sufficient chart paper for a proper trend.

When on high speed, the flux recorders are inadequate. h' o 'Miscelleacus complaints were: (1)IRMsareconfusingwith, differencesbetweenrangesunclear;(2)Displaysandmimics poorlyarranged;(3)Minimumscaledivisionsonmeters shouldbestandardizedand(4)ManyAMPmetergraduations take a while to figure out. -3.2.11. UNNECESSARYDISPLAYS(II.D)(N=24) ~ Three quarters of the sample (18) did not find any displays that were i i unnecessary or that needlessly cluttered the control panels. Six respondents offered the following remarks: o Some displays are not needed most of the time. Demaracation .would help the operator sort out those that are generally needed from those that aren't used most of the time. O .E-38

1 o The plant electrical ~mim'ic is 'not easy to folloit."It varies ~ ~ ~ ~ ~ '~ from our training experience. o The RFP rpm display is huge compared to the miniature RX ~ level and period. o Unnecessarily large meters: RFPA(B)DEVMETERN27-R426A(B) andRFPTA(B)CONTVPOSITN27-R546A(B) o Eliminate ammeters; one ameter with a selector switch by system is sufficient.. 3.2.12. ANNUNCIATOR SYSTEM (II.E)(N=27) The respondents were about evenly divided between those (13) who considered the annunciator system effective in conveying important information to the operator and those (14) who recommended modifications to increase its effectiveness. Two respondents felt that the annunciator system was effective normally but useless and a burden when a multitude of annunciators appeared during a SCRAM. Two operators called for consistent color coding of annunciators. Two operators complained of the annoying auditory alarm that was grating. ~~ One noted that annunciators should be located in a manner directly related to controls and displays on the panels. They are also not logically grouped within the matrix. Another stated that a generic local alarm with multiple inputs should come in again if a repeat individual local alarm occurs. Larger annunciators were seen needed above the 680 panels. There was felt to be room to add alarm cabinets above 680. One operator noted the lack of alarms if there is a loss of 120 VAC busses. Finally, one suggested that all reactor SCRAM signals be grouped together. C)' E-39

< V) L ~'- 3.2.13. " UNREASONABLE OR DTSTRACTING DUTIES (II.F)(N=28)" ~ l The operational sample was asked if they were required to, perform any duties that they considered unreasonable or distracting. A minority of twelve felt comfortable with assigned duties. Themajority(16) felt that some of their assigned responsibilities were either inappropriate or excessive. The unit supervisors felt strongly that fire-fighting duties were inappropriate. As one put it " Fire Brigade leadership is unreasonable. At such times the shift supervisor is expected to take on the unit supervisor's responsibilities. This may not work since the shift supervisor isn't on top of things. There is no reason for the fire brigade leader to be an SRO." Several shift supervisors concurred. One stated: "In case of a fire the unit supervisor leaves (], the control room resulting in the shift supervisor being required to do both the shift supervisor and unit supervisor's job." i Therewasalsoconcernthattheunitsupervisor(US)positionwas l becoming overloaded. One US described his role as that of being a mini-shift supervisor for his unit. The US is said to be buried in paper work with about twenty logs in the control room. The US is especially overworked during day shifts. Concern was expressed that such duties would detract from the task of maintaining cognizance over plant status. One SRO complained about "getting stuck rewriting clearance tags because the maintenance guys may be new." The station operators voiced several miscellaneous complaints regarding the following duties: (1) tagout writing and verification, (2) excessive logging and data-gathering; (3) supervising auxiliary operators,and(4)answeringnumerousphonecalls. O t-4o

F ) eOL 3.2.14. -ERRORS 01ACCIDEMYS-THAT"COULD-HAVE BEEN AVERTED " " '- (II.G)(N=23) Mostrespondents(16)couldnotpointtoactualcasesoferrorsor accidents-which could have been averted through improved control room design. Seven respondents described specific accidents or accident-inducing factors: o A reversal of B/A order of chart recorder pens and correspondingA/Bcontrolscausedanoperationalerror(See Figure 20) o MSIV Closure is sometimes missed during a Scram / Emergency due to inadequate warning on the P680 control panel. o The glass cover of a relay was broken tripping the relay andcausingasiteblackout.(SeeFigure21) o Breaker control switches are too easy to brush against while coming around the corner of P870. A rail is needed. (SeeFigure22) ~ o The Turbine Trip button should have an arming device to ~ prevent inadvertent tripping. o The overly small indications create a reliance on computer fed windows / screens which may not be the best to use in specific cases. Rateofchangecanalsobemissed(level casualties in particular - loss of feedwater was seldom dealt with quickly) o' Backpanels are not directly accessible from the primary horseshoe area .H E-41

l ip RID .Q j i.I Figure 20. The red, loop A scale } i is to the left of the i;l B scale on the recorder ( 1 l lll This B/A order is the = reVerYe"of 'ths X/B"o'r'dii' of controls shown below l O D l3 -i-eEy@ { t.u - ;.:i [WI.5 i t l \\ t T:. : Q g fid55J ~ I'- '!!].55 '.i i.JG .! ;-1 3 = ~ i ~.[E N s.L w..L 1 s "k. .. ~ . # 4 9.] gi l .ssy k1_ 1 l..i2-5 W.t W jf" ysG,.. e', < l 'y f I bd h. i ~ wM t s- - s., I I 3 mnemi, j I gq p<g\\ --1: j ( .y 3 g-g \\ s.g n ' h.? {. ATLE bh. v

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i i l O ,...i.....c 3,2:15.-1NADVERTENT 0PERATIONLP-t0NTR0t.5 ~(II.H)(N 26)- i i Ten respondents reported no risk of inadvertent control operation due

to the design, posi. tion, or labeling of controls. Themajority(16) saw opportunities for accidental or inadvertent control actuation.

I Five respondents felt that control coding techniques should be applied in differentiating pump and valve controls, and scram and i isolation pushbuttons. One added that controls that needed to be - held in place should be labeled, e.g., some RHR valves will throttle and others go full stroke. Two pointed out that the annunciator silence and turbine trip buttons could easily be confused, one for the other (see Figure 23). A trainer noted that during casualties in the simulator, students attempt to silence an alann using the turbine i trip pushbutton by mistake. Four respondents pointed to controls by the edge of panels adjacent to passageways. Projecting pistol-grip controls can get bumped or caught in clothing (See Figure 22) One noted that the location of SCRAM and NSH Initiation pushbuttons may cause inadvertent operation. 3.2.16. INDIVIDUAL RESPONSIBILITIES AND CHAIN g COMMAND (II.I)(N=29) Over two-thirds.of the sample (21) felt that their individual responsibilities and the chain of connand were clearly understood. L Only eight respondents reported difficulties in this area. Four felt that responsibilities and relationships lwere still evolving and it 4 was too early to determine whether existing confusions would be resolved. Onestationoperator_(50)pointedtoconflictingor 2 overlapping responsibilities for supervising auxiliary operators 'between the 50 and US. Another 50 was concerned about control of access to the horseshoe. Procedures state that the 50 can ask people to leave but only the US can enforce such expulsions. E-45 8 .r.,,,.m.- ....._.,,,,.,,,,..,..,o,.,m,_,,.t.,., .,,y__,,,,..

~ D lf, E' ^ h If f h f ~*M M'f - o e s;p p4 M_g '~ ' g.. p',3 n m ~~ 7F?))V;f -:KD 4: $.x, s 49,). --ar e w ~g. By a. m-i %M s ,,,t, 3

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" ',z 1RM[ m4 k"w.. fi' J., e hi' 4 ,s 3, .) g. i -' k _j. g. O. s _ [.1,@ f ?. 9 j p S i? s' c.., I o i Figure 23. The turbine trip pushbutton (left) can be confused with annunciator controls. E-46

k l ( 1wo expressed concern that roles-in an emergency (executing PEls) I were not clear. As one put it: "In the heat of battle some overlapping is possible". Another said: "the 50 is told that he is fin charge'of the shift yet, during an emergency the US takes over. This changeover of leadership is not clearly accomplished." 3.2.17. NUMBER OF OPERATORS (II.J)(N=29) Most respondents (20) felt that there was an adequate number of operators in the control room (or innediately available) to effectively operate the plant during all operating conditions. Nine respondents expressed some reservations. Two felt that another US was needed to cope with fires and because USs would be overloaded during the day shift. Theneedforanextrareactoroperator(RO) was indicated by two respondents during start-up, shut-down and emergencies. In fact one felt that there should be one operator per O ma3orboard: es01, e 80 and,870. rinaiiy, one operator suggested that an auxiliary operator should be permitted to put on a headset or answer calls during emergencies. '3.2.18. PARTICULARLY TROUBLESOME PANELS (II.K)(N=30) '~ Eight respondents found no particular panel difficult or confusing to L' operate. Themajority(22)~pointedtooneormorepanelsthatwere ~ especially troublesome. Reasons given for difficulties include lack of mimics, miniature instruments lack of control coding and. lack of demarcation. In order of freque'ncy of mention, the panels identified were(number of interviewees citing problem with the panel is shown in parenthesis): o P870 - numerous controls and unclear mimics for steam drains, heaters,andvents(10) O E-47 I

. a ;. _... i A o P680 - Small instruments, overly-complicated Feed Control System and Recirc Pump Control (7) o 0FF-GAS panel - lack of mimic lines (6) (See Figure 24) o P601-RHRandMainSteam(2) o P655 - MSIV Leakage Control (1) o P845(1) O

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l 1 -..~..~.r. r\\ N./ 4.0

SUMMARY

Figure 25 provides a summary satisfaction / dissatisfaction profile for questionnaire issues relating to procedures. Similarly, Figure 26 profiles operator attitudes towards control room design issues. For each topical area the total responses were sorted into two categories: (1) Those which indicated satisfaction with the present situation or where no change was needed in the view of operators and (2)thoseresponseswhichindicateddisatisfactionandpointedtothe need for improvement. Figures 25 and 26 provide comparisons of these sortings in percentage terms. These tables permit the reader to see at a glance that while notes and cautions used in PEls (I.A.4), as presently formatted, are generally found to be acceptable. The same cannot be said for PEI training (I.A.5 and I.K.) or PEI fomat (I.A.3). (]) These relative satisfaction / dissatisfaction comparisons provide an important input for assigning priorities in enhancement implementation planning. However, in intepreting these results there are dangers to be avoided in placing overreliance on consensus numerics. For example, in regard to the topic of manual overrides (I.A.9), sixty-eight percent of the respondents indicated that no change was needed. However,theminority(thirty-twopercent)made ~ some compelling statements regarding human factors problems associated with effecting manual overrides during emergencies. Consequently each concern expressed by the survey respondents should be reviewed for its validity and serves as the basis for identifying an HED regardless of the frequency with which a given problem is identified. s Based on this survey of operator experience some general conclusions can be made: /7 T E-50

..i... ..: U.~:.. l.- ,(n M ............... The horseshoe area is overcrowded. Due to the limited space available it is important to develop an operator station that provides sufficient laydown area, storage space for procedures, writing space..and work aids. It is also important at the same time, to leave ample room for unimpeded passageways between P680 P601 and P870. o The format of PEls is causing operators considerable problems. Alternative formats or modes of presentation should be investigated. The flowchart approach, mentioned by many 1 operators, should be evaluated. I o Training and retraining in the use of PEls is required. The operator sample surveyed is of one mind in perceiving the need for considerably more training. If the PE! format is improved, "Q. there will be a corresponding reduction in the required intensity of training. o Graphs and charts included in the PEls should be upgraded and provided in an easily accessible manner, o Improvement is needed in clarifying PEI entry / exit conditions. i o Desi~gn enhancements are required to allow safe, error-free, and [ timely manual overrides during emergencies. o Disparties between units in procedural documents and those on displays should be reconciled. Similarly related displays I should'be in comparable units. o The miniature displays on P680 are generally regarded to be inadequate and error-inducing. O E-51 .... ~....

Y( o Controls should be coded or guarded to prevent accidental or-inadvertent operation. o The support column in the center of the horseshoe blocks visibility and is regarded to be a major nuisance by operators. o The use of Unit Supervisors for fire brigade duties should be reviewed. o The comunication system should be improved to serve the needs of operators with minimum distractions. Plant coverage needs improvement. o The shift supervisor's office should be in the control room. o The location of ERIS and the process computer CRTs in the O, horseshoe shooid be revie ed to estabiish the best reiative locations to serve the needs of operators. o The location of an ERIS display for the US, SS, and the STA should be examined to establish emergency use requirements. ~ o Controls that are spring-loaded should be identified and a means should be provided to allow them to be operated more easily. o Troublesome panels identified by operators should be enahnced. The panels considered most difficult to operate were P870, P680, and the 0FF-GAS panel, n E-52

L ^'* ]IO CHANGE REC 0 WINDED IMPROVDENT NEEDED ......w b.E.E E E., E E E 'E o 1 \\ I. PROCEDUPIS I i A.1 STORAGE LOCATIO'N M 33% i l6711i39%j A.2 LAIDOWN SPACE MM MI 61 5 l l A.3 FORMAT /LATOUT 23% Ememmm 77% A.h NOTES / CAUTIONS '83% M 17% i i 1.5 TRAINING l I 15% mmm-3 85%l t l l A.6 IE77.L OF DETAIL 65.5% N- ~37.5% l A.7 CHARTS AND GRAPHS 29% m :EEEER N 71% i I A.8 ENTP.IES/EIITS 48% museummus -.. m m 52% l l } I I~ A.9 MANUAL OVERRIDES 68% c.a..,,u,.- u*. m 32% i i i i I I B. INFORMATION/ CONTROLS

• 55% L pummmmarim133summs 45%

l C. VISIBILITY-DISPLAYS l35% m.- mm 65%. i i D. PROCEDUPI-ERRORS 50% ggem-g ,50% I i 1 1 j E. UNDERSTANDI!U PEIs 13% mmmmmmenumeners 87% l' i i t F. DIFFICULT PEIs 8% m- - 92% l l } 0. VAGUE PEIs 62.5% M MM 37.5% l l i l H. SOIs, ARIs, 10Is 52% ,M m mmm 4s% l I. USE!ISS PEI STEPS 82% Mmm M 18% J. DISSOCIATED C-Ds 40% mm mmm 60% I i E.. SUFFICIEl.7 PEI TRN3 22% Em m M 78% g Figu.re 25. Satisfaction / dissatisfaction profile for procedural factors. t E-53

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II. CONIROL ROOM s A.1 SRIFT COVERAGE 58% - mME42% A.2 CONTROL ROOM ACCESS 83* m 17f ~ i l I A.3 CONTROL PANEL LAYOUT 68* M 32% i I.I I i A.la COMMUNICATIONS l 46% N I M 54% i i l A.$ INFORMATION FIUri 82% EMM,18% i l l A.6 FURNITURE /QUIPMDiT 38% M m 2 62% t i l l A.7 COMPUTERS ,75% - ~ ~ ,. -., em 25% l B. DIFFICULT CONTROLS 56%, ~ mg 44% k I l l l ,,C. CONFUSING INDICATORS " 17% -* -' " " " " 83% ll D. UNNECESSARY DISPLAYS 75% + " ~ + mM 25% I E. ANNUNCIATOP.S 48% gmll33m-., 3 52% I l F. UNREASONABIE DUTIES i 43% E-m M 57% i j l 3 G. ERROP.S DUE TQ CR DESG 70% ~Nm W 30% I l l l H. INAD7ERIENT OPERATION l 38% M'm 62% I I. CHAIN OF COMMAND 72% N mmM 28% J. MANNING ADMUACY $9% mm - M 31% E. TROUBLESOME PANELS 27% rem mMM 73% i O , Figure 26. Satisfaction / dissatisfaction profile to control room factorp.

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4 i lf aj g THE CLEVELAND ELECTRIC ILLUMINATING CDMPANY 'I /m ;'...e. MEMDRANDUM O I se leas.e, wieli to..i. 3 .ei F($p '} [0 .-.m o o M rnow B. J. Panfil cA7c May 18,1984 .s-- ~e-2. .') PHo N E5686 nooM TOl d sueJEc7 ~ OPERATOR SURVEY ji'j .PNPP OPERATOR SURVEY - EXPERIENCE UPDATE lE [2 INTRODUCTION TO QUESTIONNAIRE In response to a post-TMI NRC requirement, your utility is conducting an emergency ^ procedure (PEI) task analysis and operating experience update to identify and correct deficiencies in the areas of operator to procedure compatibility, procedure to plant compatibility, and operator to machine interface to minimize the potential for human .I error. This analysis is performed by a BWROG survey team composed of human factor ..j engineers. "1 0 Complete the attached questionnaire basing your response on your operational experience and knowledge of your plant's emergency procedures (PEI's), your control room, and interfacing systems. Please do so without discussing your detailed responses 'l with other operators completing this survey. If additional space is needed, please use the attached comment form. This survey provides you with a valuable opportunity for ,,A applying your knowledge and experience towards improving your control room and operat- . ',,' V ing procedures. Your honest opinions are not only welcomed, but needed. Please submit your completed questionnaire, including this cover letter, to the '33 Human Factors Unit via B. Panfil (TO1) by the deadline date, June 1,1984. 9 .'i 4 .i l I 1 3 t 1 .J ,1 J q BJP/pr y C/ E 3 1

s .f e b. 2; Page 2 '? (~], May 18, 1984 [,(7._/ 1t ,....,. ;......f.... n 5 f5.* 2 I1 OPERATOR SURVEY - EXPERIENCE UPDATE LV 'z.; QUESTIONNAIRE .,q y Job Position: + Years Experience: Commercial Nuclear Navy Nuclear Fossil Date of First License: RO SRO 2 ".?

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...c. .'-i Date of Certification: RO SRO .i ' 7) Education / Degrees: f i Age: Sex Attended License Training: Yes No ,m I. Procedures A. In regards to the PEI's, would you recommend any changes in the following areas: Al Storage location in Control Room. [,. A2 Laydown space in Control Room A3 Format and page layout A4 Use of notes and cautions A5 Training s ? r A6 Level of detail A7 Supporting charts and graphs e q AB Entry conditions, exit conditions ~ j s.,' A9 Use of manual cverrides . i. J-E-57

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• Page 3 May_18, 1984 06 -,

. s, _ f' B. Based on your operational experience or simulator training, does the Control Room lack any information or controls needed to carry out the actions required 4 f by the PEI's? i-6 C. Are any recorders or indicators 1ccated such that they are difficult to see . during emergency operation? s D. Based on your operational and simulator experience, have any errors or incidents occurred which could have been averted through improved procedures? E. Have you experienced any problems using or understanding the PEI's? 2 F. Is there a particular PEI which you consider difficult or confusing? C. Have you found steps in the PEI's which are too vague or generalized, or which do not provide enough detail to determine exactly what actions are required by -(~x-you as the operator? H. Have you found it necessary to refer to other procedures (SOI's, ARI'e, IOI's) in order to carry out the actions required by a PEI because the PEI contains insufficient detail in its action statements? 5 I. Are there steps in any of the PEI's which you consider useless or not essential to perform the intended actions of the PEI? J. While verifying an action you performed has had the desired effect, have you found it necessary to move away from the related controls to read an indicator? K. Do you feel you have been sufficiently trained to carry out any action required by any PEI? I I-M u 4 % 7 f-n.

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.L.. Of* 7 F y {- Page 5 .,, p May 18, 1984 s s's 4 II.' Control ~ Room b ] A. In regards to the control room, would you recommend any changes in the 't. following areas? P J i z 's Al Shift coverage ?-) - A2. Control Room access }' A3 Control panel layout 2,. A4 Communications l' A5 Information flow A6 Furniture or equipment ~" -A7 Computers A8 Others ? B. Are any controls difficult to operate? C. Are any recorders or indicators confusing to read? i D. Do you feel any Control Room displays are unnecessary, or needlessly clutter the control panels? u,.. E. Do you consider the present annunciator system to be effective in conveying important information to you? F. Are you required to perform any duties that you consider unreasonable or distracting in your responsibility as an SPO or RO? 'O G.. Based on your operational experience, have any errors or incidents occurred fd which could have been averted through improved Control Room design? .s ~i s, . ~.. _..... _. _ _ _ _ _ _. _, - _, _...._.-, __.___,_..,_E-60 _, _

m y T e s-h Page 6 S May 18, 1984 t.' f li\\ -i R. Are any controls designed, positioned or labeled in a manner that causes risk of inadvertant operation? -r I. Are individual responsibilities and chain of command clearly understood J during all operating conditions? 9 3.., J. Is there an adequate number of operators available in the Control Room (or immediately available) to effectively operate the plant during all conditions? K. Is there a particular panel which you consider more difficult or confusing to operate than the others?

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RESPONSE

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(~% .,i V O ATTACHMENT F DETAILED CONTROL ROOM DESIGN REVIEW TEAM RESUMES Sharen K. Eckert James

w. Howard Joseph L. Seminara e.

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.:... _ _ _...... ~ _.. ^ 7.. l ~* SHAPEN K. ECAEPT ( ). ~ RESUME i EDUCAT IDriAL ' EACl GFDurtD D. O. IN MATMEMATICE, MEITHItJETER {DLLEGE, NEN WILMINGTON, PA, 1 96.7 4 M. S. Ira MECHAt41 CAL ENGINEERING, THE UNIVEPIETY DF RPI:DNA, TUCrDu. API:DNA, 1970 CDUPrEwDPr Ita human FACTDPr ENGIt4EERING AT FAN Jure STATE V8 J I UE WI I T Y AND.$ tap 4FDPD dtJI VE PE I Ti, FUPEUING A PHD IN INDUITPIAL EraG I NEER I r4G, 1973 - 9 HUMAN FACTORS WDPl! E>:PERIENCE 1979 - 1993 CDNrVtTANT TD uErTINGNDUfE ELECTPIC REKEAPCH AND DEvELDFMENT CENTER, PITTrxUPGH, PENT 45YLL ANI A f CONTPIxUTED TO THE ITEPATIVE DESIGN FPDCEFI FDP THEIP ADVANCED CONTPDL RDOM, SPDS, TSCr ~ SAFETY SYETEM DIEFLAYF, AtJD CLINCH RIVER bpEEDEP EEACTDP FPQJECT. 1973 - 1979 HUMAN FACTDPr 5FECIALIET IN THE SPACE SYETEMF D! u 2 7 2 DtJ DF LDCF:NEED MIrrILEs AND SPACE COMPANY, EUt dtJYV AL. E e CALIFDPNIA PAWTICIPATED IN THE HUMAN FACTDPE ETUDIEE FDP THE ELECTRIC PDuEP RErEAPCM INITITUTE. (EF FI). WAE A FPINCIPAL I NVEETI G ATDP IN EPRI's FPDJECT 501-3 TD DEVELDF HUMAN FACTDPs METwcDr FDP l-NUCLEAR CONTpDL RDDM DErIsNr. FDPMULATED AN ANALYTIC ETPATEGY FDP GATHEPING TAEK ANALYTIS INFDeMATION AND DEPIVING OFEPATIDNAL CONTPDL ArJD INFDPMATION REDUIPEMENTr. PERFDeMED TArM AreALYf25 FDP THE PEACTOP CDNTPDL PANEL. DE-VELDFED THE SUIDELINES FDP INCLUDING HUMAN !~- FACTOPE IFSUES AND CONCEPNS IN THE DEVELDFMENT I. pp THE ADVANCED CDNTPDL PDDM. L CONDUCTED A PEv!Ew FDP EPRI Dr vur MUMAN FACTDPr 'IMPLICATIDNF DF TMI. REv3ENED THDUrAraDs DF PAGEr DF TEFTIMONY, IDENTIFYING EVENTE DUPING THE INCI-DENT TD WHICH HUMAN FACTDPF EMDMTCDMINGE MAY H As E CDNTRIPUTED. 'O e WWh ia_

l. ~. '. '. = '..... _ ~ r l ,\\_( HUMAN FACTOFS 8IDPK EXPEPIENCE, CONT'D \\ H.; MAN FACTcPs SPECIALIrr AT LDCesEED, CONT'D ~ r l*lD P V E D ON TEVEPAL MILITARY FPDJECTJ I Nt/cLV I NG C Drit1 A N D At4D CQHTPDL ETATIONS. DEI / ELOPED TAIM AND DPERATIDNAL P E C'v ! P E ME NTr. PApTICIFATED IN t THE DEFIGN AND DEVELOPMEt4T OF ItJFDPMATION ETPUC-70*EE AND ACCETFING ECHEMEI* DIEFLAY FD AMATT ! tJG o UFER INTEpACTION ITPATEGIEJ At3D AAPDtsAPE DEFIGN, e AtJD WDPFITATION LAY-3VTE. i I SEMINAPI / UDPKSHOPO / TUTOPIALS PARTICIFATED Af A FMINA*Y PPEEENTEP IN THE FDLLCHING WQPVIMQFE AND Tv70pIALf! MAY 1979 WCPvfHOP DN HvMAN FACTCPs IrrvEs IN SOFTWAWE-I NT EN F l e/E SYETEMI, GIVEN FDP LOCVMEED, N A8/Y, AND AI= FamCE FEprDNNEL (SUHert V AL E, CA) SEPT 1979 HUMAN FACTopr ENGINEEPING IUTQpIAL FDs BAICDCp (3 1.II L C O V FERIDNNEL (LYNCHIvpG9 VA) DEC 1979 $ Emit 4Ap DN HvMAN FACTcPr IN TwE CcNT==L P=cet PDs x l.IE*ET I NGHOU T E FEDELE IH8/DLVED Ct3 THE CLINCH PIVER BREELEm PEACTOP PPDJECT (PITTsrvPGs. PA) 34N 1980 8.lcavrwom cN HvMAN FACTear ENGINEEPING IN PouEn PLANT DEFIGN. OPEpATIoN, AND MAINTENANCE

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( s Y FFm 1992 HUMAN FAeTo=r ENGINEEp!NG SEMINAM FDP GILIEmT AND AEIDCIATEF (PEADING, P A> MAN 1992 CONT =ot Room HvMAN FACTO =r SEMINAM FDP WEETINGHOUIE s Em?ctJNEL (PITTravPGH, PA) map 1982 TUTQw!*L DN HUMAN FACTDPs AspECTr er FowEP PLANT ~ CoNTPDL Rooms, rFDNIQPED B Y Te-E 7HEDIfM PauEP I4DAPD -( NYN A T HAMN

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, _ _.a _. _ m ...E'.E_... g 't RESUME James W. Howard POSITION TITLE: Engineer SPECIFIC EXPERIENCE AND QUALIFICATIONS: l Mr. Howard is currently, an engineer in the Plant Performance Engineering subsection of General Electric's Nuclear Energy Business Operation. He is responsible for the performance analysis of nuclear power plants. In that capacity, he has evaluated the capabilities of various power plant safety systems to prevent or mitigate the consequences of postulated accidents and abnormal transients. He has also perfonned plant transient - response analyses to justify plant perfonnance improvement programs. He has also been involved in the detailed review and assessment of control room designs from the standpoint of human factors engineering considerations. Mr. Howard has over six years of engineering experience in the nuclear field. Mr. Howard's experience in engineering while working at General Electric has 8 included analysis of containment response to postulated accidents, develop-ment of containment response computer analysis models, testing of emergency core cooling system components and program management of containment and vessel dynamic load evaluation programs. EDUCATION: B.S. Mechanical E,ngineering - California State Polytechnical University 1978 N.S. Mechaniral Engineering - University of California 1984 ~ OTHER TRAINING: Edison Engineeri.ng Program (GE. A,B,C Courses) 1980 Problem Solving and Decision Making - Kepner 7 Tregoe .1961 BWR Owners Group Control Room Survey Workshop', 1983 c0 ./

~ ' ~ ~.... _ = - n._._ JOSEPH L. SEMINARA, HWAN FACTORS CONSULTA!.T l(',. .Mr.. S*-h=-a.has thirty years experience in the human factors engineering field. Since 1955 he has worked with a variety of military and aerospace organizations including the Rome Air Development Center, the Feltman Army Ordnance Research a'nd Engineering Laboratories, United Technology Center and the Lockheed Missiles and Space Company. He has contributed.to a wide range of complex systems including the Polaris Missile, lunar vehicles, and the Space Shuttle Orbiter. Since 1975, Mr. Seminara has been exclusively concerned with human factors aspects of power plant operation and maintenance. Under EPRI sponsorship, he conducted pioneering studies to imestigate human factors issues in nuclear power' plant control room design and enhancement avenues. In parallel with this research he has also been responsible for reviewing human factors con-cerns in the area of power plant maintenance. This work has produced the following reports: -EFRI NP-309 -- Human Factors Review of Nuclear Power Plant Control Rocs Design, March 1977 IPRI NP-1118 - Human Factors Methods For Nuclear Control Room Design: Vol. I. Control Room Enhancement. Nov. 1979 Vol. II. Current Design Practices. Nov. 1979' Vol. III. Comentional Control Room Design. Feb. 1980 Vol. IV. Advanced Control Room Design. Mar. 1980 EPRI NP-1567 - Hu=an Factors Review of Power Plant Maintainability, Feb.1981 IFRI NP-2360 - Hu=an Factors Methods For Assessing and Enhancing Power Plant Maintainability, May 1982 i ~ EPP.I N?-2h11 - Human Engineering Guide For Enhancing Nuclear control Rooms - May 1982 (subcontract to the Honeywell Corporation) - Mr. Se=inara has also supported the INPO human factors program during its ~ formative stages and has consulted with the GE HWROG in the performance of control room reviews. He is presently involved in a review of the PG&E Diablo Cagon control room. . Mr. Seminara holds a Masters degree in _ Industrial and Exper$Jnental Psychology from New York University (1952). He is a Fellow in the Human Factors Society. O In 1983 he served as a technical expert in Korea under the auspices of the International Atomic Energy Agency of the UN. Since 1971 he has visited all - of the Eastern European countries as-part of the Scientifi',Ixchange Program c administered by the National Academy of Sciences..' 4 O c.ns .,,,,,v

8

t. h Mr. Seminara is the Human Factors Society's selection for the annual JACK' A.

I. award. This award is granted to human factors specialists who have made highly . s.ignific, ant coptributi-ons in, applying, huma. facters to a new area __of e,ndeavor...Kr. Senisara was honored for his original work in the operational and maintenan:e aspects of nuclear power plants. .Mr. Seminara has conducted human factors w:rkshops for the US power industry and has been invited to present, these workshops in Israel (1981) and5weden (1952). From mid-December 1983 to mid-January 198h, he will present a workshop in Israel dealing with hunan factors aspects of maintainability effe:tiveness in power plants. e 9 0

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.c '.i ' k SELECTED PUBLICATIONS IN HUl%N FACTORS .b ENGINEERING OR ERGONOMICS o Seminara, J.L., and Smith, D.L., Remedial Ergonomics, Applied Erconomics, In Press. o Seminara, J.L., and Parsons, S.0., Nuclear Power Plant Maintainability, Apolied Erconomics, September 1982 Vol.13. No. 3, pps.177-189. o Seminara, J.L., Human Factors Methods for Assessing and Enhancing Power Plant Maintainability, Electric Power Research Institute, Palo Alto, CA., EPRI NP-2360, May 1982. o Seminara, J.L., and R. W. Pack, Comunication Needs of the Nuclear Power Plant Operator, IEEE Transactions on Power Apparatus and Systems, April 1982. Vol. PAS-101, No. 4, pps. 792-796. o Seminara, J.L., and S. O. Parsons. Human Factors Review of Power Plant ' Maintainability, Electric Power Research Institute, Palo Alto, CA., EPRI NP-1567 February 1981. o Seminara, J.L., et al, Human Fact' ors Methods for Nuclear Control Room Design, Electric Power Research Institute, Palo Alto, CA., EPRI NP-1118, Q Sumary Volume, June 1979, Volume I: Human Factors Enhancement of Existing Nuclear Control Roo6s.. ') November 1979 Volume II: Human Factors Survey of Control Room Design Practices, November 1979 L Volume III: Human Factors Methods for Conventional Control Board Design, L February 1980 Volume IV: . Human Factors Considerations for Advanced Control Board Design, l. . March 1980. o Seminara, J.L., Gonzalez, W.R., and Parsons, S.O., Human Factors Review of b Nuclear Pow ~er Plant Control Room Design Electric Power Research Institute, Palo Alto, CA., EPRI NP-309, November 1976. ~ o Seminara, J.L., and Shavelson, R.J., Lunar Simulation, Human Factors,1969, t .. Volume XI No. 5, pps. 451-462. ' o. Seminara, J.L.,~ and Kincaid, W'., Control Task Performance in the Lunar l Visual Environment Journal of Aerospace Medicine, Vol. 40, No. 4. April 1969. o Seminara, J.L., and Shaveison, R.J., Effectiveness of Space Crew Parfonunce Subsequent to Sleep _ Arousal, Journal of Aerospace Medicine,1969, Vol. 40, No. 7, pp. 69. i E . o. Seminara, J.L., Simulating the Lunar Astronaut's Environment, Spaceflight: Journal of the British Interplanetary Society,1969, Vol. XI, No. 2, pps. Q 56-62. o Seminara, J.L., simulation of Manned Lunar surface Operations, Journal of j Spacecraft and Rockets Vol. 5, No. 8, August 1968. o Seminara, J.L., and Ketcham, R.L., Con 6atting Confusion,in Control Panels. Machine Desion. April 1968. o L

N..:. :-......:.. ...: l ~ -- h -. SO ki o Seminara, J.L., Parsons, 5.0., and Shavelson, R.J., Sensory Discrimination F and Attitudes Toward Water Reclaimed from Urine, Journal of Aerospace Medicis.e,

September 1967, Volume 38, No. 9, pps. 905-908.

o Seminara, J.L., Shavelson, R.J., and Parsons, 5.0., Effect of Reduced Pressure on Human Performance, Human Factors,1967. Vol. IX, No. S. pps. 409-418. o Seminara, J.L., Humanizing a Moon Rover, Machine Design, November 24, 1966. o Seminara, J. L., and Parsons S.O., Human Factors Engineering, The Rule, _ December 1966, Vol. 7, No. 2. o Seminara, J.L., and Gerrie, J.K., Effective Mockup Utilization by the Industrial Design - Human Factors Team, Human Factors Journal, August 1966, Vol. 8, No. 4, pps. 347-359. o Seminara, J.L., Human Factors Shape Molab, Machine Design, May 26, 1966, pps. 148-153. o Seminara, J.L., Warning Systems Design, Machine Design, September 30, 1966, pps.106-116. o Seminara, J.L., Seventeen Ways to Stop Control Accidents Control Engineering, November 1964. o Seminara, J.L., Human Factors Engineering and Electrical Connector Failures, ~ Machine Design, August 1964. Seminara, J.L., Display Systems Design, Machine Design. November 7,1963, pps. O.o 166-176. .i .o Seminara, J.L., and Parsons, 5.0., Skills Inventory System, Machine Design, February 1963. o Seminara, J.L., Accuracy and Speed of Tactual Reading, Ergonomics, January 1960, Vol. 3, No.1, pps. 62-67. o Seminara, J.L., Self-Luminous Materials, Materials in Design Engineering, September 1958, pps. 89-92. ~ o Seminara, J.L., Research in Human Engineering Aids Design, Industrial Laboratories, May 1958, pps. 20-21. ~ o Seminara, J.L., Designing for Human Strength Machine Desien, May 28, 1959,. ~ pps. 89-92. o Seminara, J.L., Control Identification, Machine Design, June 25, 1969, pps. 137-139. 'o Seminara, J.L., Design for the Sense of Touch, Industrial Laboratories, September 1959, 'pps. 5-8. o Seminara, J.L., When Equipmbt Says It In Color, Product Engineering. September 14,1959, pps. 51-54. O J -}}