ML19347F703
| ML19347F703 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/10/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Pollock M LONG ISLAND LIGHTING CO. |
| References | |
| NUDOCS 8105260074 | |
| Download: ML19347F703 (28) | |
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MAY I 0 1981 Docket No. 50-322 d
42 Mr. M. S. Pollock C
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Long Island Lighting Company
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I 175 East Old Country Road Hicksville, New York 11801 4
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Dear Mr. Pollock:
SUBJECT:
CONTROL ROOM DESIGN / AUDIT REPORT - SHOREHAM Enclosed is our Human Factors Engineering Control Room Design Review / Audit Report for Shoreham Nuclear Power Station, as a result of the site visit on' the week of March 30, 1981, A meeting has been set for May 29, 1981, and the purpose of the meeting is to discuss your proposed action to correct the human factors deficiencies noted in this report and the. schedule for implementing these actions.
Sincerely,
/
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W Robert L. Tedesco, Assista Director for Licensing Division of Licensing
Enclosure:
As stated cc w/ enclosure:
See next page T8105 2 6 0 0'fY 9
k' Mr. M. S. Pollock Vice President-Nuclear ~
-Long Island Lighting Company 175 East Old Country Road Hicksville, New York '11801 ces:
Howard L.'Blau, Esq.
Honorable Peter Cohalan Blau and Cohn, P.C.
Suffolk County Executive -
217 Newbridge Road County Executive / Legislative Building Hicksville, New York 11801' Veteran's Memorial Highway Hauppauge, New York 11788 Jeffrey Cohen, Esq.
Deputy Commissioner and Counsel David Gilmartin,' Esq.
New York State Energy Office Suffolk County Attorney Agency Building 2 County Executive / Legislative Building Empire State Plaza Veteran's Memorial Highway Albany, New York 12223 Hauppauge, New York 11788 Energy Research Group, Inc.
MHB Technical Associates 400-1 Totten Pond Road 1723 Hamilton Avenue - Suite X Waltham, Massachusetts 02154 San Jose, California 95125 Irving Like, Esq.
Stephen Latham, Esq.
Reilly, Like and Schnieder Twomey, Latham & Schmitt 200 West Main Street P. O. Box 398 Babylon, New York 11702 33 West Second Street' Riverhead, New York 11001 J. P. Novarro Project Manager Joel Blau, Esquire Shoreham Nuclear Power Station New York Public Service Commission l
P. O. Box 618 The Governor Nelson A. Rockefeller Bldg.
Wading River, New York 11792 Empire State Plaza i
l Albany, New York 12223 i
W. Taylor Reveley, III, Esq.
Hunton & Williams Ezra I. Bialik P. O. Box 1535 Assistant Attorney General Richnend, Virginia 23212 Environmental Protection Bureau New York State Department of Law Ralph Shapiro, Esq.
2 World Trade Center Cammer & Shapiro New York, New York 10047 9 East 40th Street New York, New York 10016 Edward J. Walsh, Esq.
General Attorney Long Island Lighting Company 250 Old Country Road Mineola, New York 11501 Resident Inspector /Shoreham NPS c/o U.S. Nuclear Regulatory Commission P. O. Box B Rocky Point, New York 11778 4
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HUMAN FACTORS ENGINEERING
' CONTROL ROOM DESIGN REVIEW / AUDIT REPORT OF-SHOREHAM NUCLEAP, POWER STATION LONG ISLAND LIGHTING COMPANY A human factors engineering preliminary design review of the Shoreham control room was performed at the site during the week of March 30 through April 3, 1981. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. This report was pre-pared on the basis of the HFEB's review of the applice t's Preliminary Design Assessment and the human factors engineering preliminary design review performed at the site. The review team was assisted by human factors con-sultants from Biotechnology, Inc. (Falls Church, Virginia) and from Lawrence Livermore National Laboratory (University of California, Livermore, California).
Observed human factor design deficiencies were given a priority rating of one to three, (high, moderate, low), based on the increased potential for operator error and the possible consequences of that error.
The following sections are numbered to conform to the guidelines of the draft version of NUREG-0700 and summarize the team's observations of the control room design and layout of the control room operator interfaces with that environment.
4
HUMAN FACTORS ENGINEERING CONTROL ROOM DESIGgREVIEW 3
Audit Report SKREHAM NUCLE 5R POWER STATION s
- 1. WORKSPACE CATEGORY FIf0ING 2
1.
The computer console obstructs the view of the MXP and VCl cuxiliary panel 5 from the seated operator position at~the operator's desk.-
1 2.* 1he security console is umecessay in the control room.
It obstructs movement and obstructs the view of the MXP panel fr m the operator desk and the reactor control console.
1 3.
Construction of the' supervisor's office is not complete. The adequacy of visual and voice contact between that office and the control roo.n could not be evaluated.
1 4.* Grounding cable covered by a metal sleeve on the floor between the operators' desk and the reactor control console is a tripping hazard.
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1 5.
Tangled and kinked sound powered pho,ne cords lying on the floor are a tripping hazard. Use of non-kink or self retracting cords is recommended.
2 6.
Controls trounted on vertical boards of Panels 601 and MCB, which are 30 inches from the front edge of the benchboard, are difficult for short persons to reach.
Recommended: 24 inches maximun reach distance to any control.
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3 7.
The amunciator panels on Panels MXP, VCl, and VC2 and i
on all of the back panels are not tilted forward to enhance readability.
2 8.
tiand held radio (walkie-talkie) transmission and reception is variable between the control room and other areas of the plant. Hand held radios camot communicate between persomel in the control room and in the reactor building.
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- Discrepancy also noted in Long Island Lighting Company report of Preliminary Hunan Factors Engineering Recommendations.
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SFOREHAM NUCLEAR POWER STATION Control Room Design Review Audit Report i
- 1. WORKSPACE (continued)
CATEGORf FIf0ING,
1 9.* Sound powered phone jacks for the Remote Shutdown Room are located outside of the room behind the entrance door.
1 10.
No sound powered phone headsets are stored in the Remote Shutdown Room.
1 11.* Emergency equipment is stored in temporary storage locations. Operational storage, identification, availability, adequacy, and maintenance of emergency equipment could not be evaluated.
1
- 12. No provisions are m5de for speech transmission or commmications while wearing energency breathing apparatus face masks.
I
- 13. Docunentation is stored in temporary shelves on the back side of the computer console. Operators at the operator desk or the reactor control console must walk around the computer console to obtain reference docunents Final design and organization of reference document storage in the control room is unknown.
1
~ 14. There are no emergency procedures stored in the Remote Shutdown Room.
I
- 15. Procedures are not adequately cross ' referenced. Could not determine whether adequate procedures exist for:
a.) Periodic testing of emergency alarms and communications systems, b.) Periodic testing of sound powered phone
- systems, c.) Periodic inventory and inspection of emergency equi ynent, and d.) Training and practice in use of energency equipment.
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m SHOREHAM NLCLEAR POWER STATION control Room Design ReviGo Audit Report 5
- 2. WCRKPLACE ENVIR0tNENT CATEGORY FIf0ING,
1 1.
Permanent control room ventilation system could not be evaluated since it is not operational. The temporary ventilation system has excessive air flow.
1 2.
The lighting of the operational control room could not be accurately evaluated because ceiling diffuser
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panels had not been installed below the light fixtures.
3 3.
There are no procedures or plans to conduct periodic lighting ir. tensity surveys in the control room.
1 4.. The emergency DC lighting in the back panel areas is inadequate. Measured lighting 111minsnce ranged from less than one (1) foot candle to seven (7) foot candles.
Recommended: 30 foot candles minimum for safety related panels and 7.5 foot candles minim m for non-safety related panels, 1
5.
No emergency lighting is provided in the Remote Shutdown Room.
1 6.
Contrast between displays and the panel background exceeded the maximum recommended 1:3 luminance ratio j
at many locations in the control room:
a.) Contrast between dark meter faces and panel backgrounds had 1minance ratios ranging from 1:3 to 1:10, Contrast between the CRT displays and the -
b.) l 603 background had 1minance ratios of 1:5.
Pane 3
7.
Tonnal ambient noise levels in the control room could not be measured accurately because of construction activities.
1 8.* There is,no lainp test capability 'or other positive means ofedetermining failed indicating lights except for annunciator lights.
2 9.
Light bulb replacement and service of all Weston meter displays nust be done from the back of the panel cabinet.
1
- 10. Changing light bulbs of indicator Jights for switches controlling air and motor operated valves is unwieldy and requires a special wrench / extractor that is difficult to use.
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SHOREHAM NUCLEAR POWER STATION Control Room D: sign Revicw Audit Recort.
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- 2. WORKPLACE ENVIRONMENT (Continued)
CATEGORY FIPOING s
1 11.* Maintenance tags hanging down on vertical panels can obscure indicator lights and labels of switches mounted below.
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SFOREHAM NUCLEAR POWER STATION Control Room Design Reviea Audit Report
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- 3. ANNUNCIATORS AND AUDITORY SIGNALS CATEGORY FIPOING i
1 1.* The annunciator panel identificatt,n scheme is inconsistent and does not follca a conventional sequential order around the main control boards..
1 2.
The controls provided for operator response to the annunciator system provide only SILENCE, ACKNOWLEDGE, and TEST controls.
Reconsnended: provide SILENCE,' ACKNOWLEDGE, RESET, and R51 controls for annunciators.
1 3.
No first-out alam system is provided in the annunciator system to identify trip initiating events.
1 4.
There is no audio o~r visual annunciator indication to signify that an alarmed condition has cleared. Once an alarm occurs, the annunciator tile remains illuninated until the operator presses the Acknowledge
' control. Then the tile illumination turns off if the alarm has cleared.
1 5.* Annunciator tile locations are not ident* fled by a matrix identification scheme with the matrix location
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code inscribed on each tile. Each tile is number i
coded but the there is no systematic correlation between the number code and the tile location. Tiles are not physically keyed to prevent placement in an incorrect location.
4 3
6.
The flash rate of annunciator displays (approximately 1.5 - 2 flashes per second) is slower than recommended.
Reccanended: 3 - 5 flasi.as per second flash rate.
1 7.
Failure of an annunciator flasher circuit, which may control flashin0 indicators on more than one annunciator panel, does not necessarily result in steady illunination of the annunciator tiles that were flashing.
If flasher failure occurs the affected annunciator tiles will stay either in.tbe steady ON or the steady 0FF condition, depending on their CN/0FF state at the instant flasher failure occurs.
3 8.
Some annunciator legends are difficult to read because of inadequate spacing between characters and because character proportions are too thin.
1 9.* It is difficult to distinguish whether dark red colored tiles, amber colored tiles, backlit red tiles, and backlit green tiles of annunciator displays are ON or OFF.
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SK)REHM NUCLEAR POWER STATION Control Room Design ReviGo Audit Report 5
- 3. ANNUNCIATORS AtC AUDITORY SIGNALS (Continued)
CATEGORY FItOIN_G 1
10.* Annunciator response controls are not easily.
identifiable from other controls and do not have special markings or demarcation to make them stand out
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as individual control groups from other controls nearby. The green, red, and black collars around the individual annunciator control pushbuttons are not adequate to distinguish the annunciator controls from other pushbutton controls that are also color coded by use of colored collars.
I
- 11. Panels 654 and 6M Annuncistor response controls have one more button than is used on the other panels (a RESET button).
I 12.
Annunciator alarm control pusttuttons for Silence, Acknowledge, and Test can be operated in any sequence.
1
- 13. Alam procedures are not keyed to annunciator panel identifiers and annunciator tile matrix coordinates.
They are indexed only to the four digit code on each tile which is not systematically related to the tile location.
I
- 14. There is no input to the Annuciator Inoperative alarm when the HPCI and RCIC controls are switched from AUTO to MAMJAL.
1
- 15. Localizing quality of audible alarms is not adequate.
While the frequencies of the annunciator alarms at the RCC benchboard and at the RWC and RCIC benchboard are different, their separation is not sufficient to provide a clear localizing quality.
It is difficult to determine which annunciator panel is alarming when only one alarm is sounding.
1
- 16. The five coded audible station emergency signals, which can be broadcast throughout the plant by the Gai-Tronics system, have not been assigned to specific station emergency conditions.
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l 17.* Annunciator alarms on the feedwater and electrical areas of Panel MC8 are not loud enough. They are barely audible above the 64 cS(A) ambient background noise level.
S WREHAM NUCLEAR POWER STATION Control Room D: sign Ravicw Audit Report
- 4. CONTROLS CATEGORY FIPOING 3
1.
The Recirculation Master Flow Control at the left end of Panel 603 is beyond convenient reach of the reactor operator manipulating the reactor ccntrol rods at the i
center of Panel 603.during reactor startup and power level changes.
3 2.* Recirculation Master Flow Controller on the reactor control benchboard Panel 603 should be grouped on the reactor recirculation benchboard Panel 602 with the Recirculation A and B Flow Controllers.
2 3.
The IRM range switches on Panel 603 are laid out in a mirror image arrangement of switch locations, colors, and labels with an unconventional left to right sequence ACEB - HFDB.
4.* J handle controls are too close to the front edge of
.t the Panel 602 benchboard and are vulnerable to accidental actuation.
2 5.* A violation of "open-right", "close-left" convention exists on the MAIN TLRBIE LO Bailey control on Panel MCB.
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6.
The RCIC Reset keyswitches on Panel 602 rotate in reverse direction from the normal control room cc.wention of clockwise to reset.
1 7.* The switch position does not match the label, with.
label being incorrect on the Hydrogen Recombiner Panel.
2 8.* The top two switches on Panel ACH are too high for easy operation.
1 9.* Lack of contrasting color marking makes switch handle arrows on Panel 602 difficult to see.
1 10.* Inconsistent colcr coding of throttle valve switches occurs on Panels 602 an'd MC8.~
l
- 11. An inconsistent use of different types of "
switches for same function exists between handles on Panel 602 and pushbuttons on MC8.
2 12.* The Remote Shutdown panel inappropriately uses scme green switch handles. Green is used elsewhere to identify throttle valves.
SHOREHAM MUCLEAR POWER STATION Control Room Design Revicw Audit Report.
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- 4. CONTROLS (Continued).
CATEGORY FIFOING i
1
- 13. There is an inconsistent use of switch handle shapas in several locations (Panels MCB, 601, 602).
2
- 14. The R8 SVC WATER override suitches under annunciator Panel E on Panel MCS rotate in two directions instead of only in one direction.
1 15.* The small diameter, flush mounted pushbuttons on Bailey flow controllers are difficult to depress.
I 16.
The backlit pushbuttons on MC8 use Ody one bulb per switch and do not have a provision for a lamp test.
3 17.* The removable handle allows dirt to get into the switches on the MC8.
3
- 18. No specific storage hook or clip is provided on Panel MC8 for the removeable handle that is used to manipulate several switches in the emergency power distribution system.
1 19.* The REACTOR MODE switch is very difficult to turn.
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3 20.
There are inconsistencies in key tooth orientation of key operated switches.
2 21.
The key can be removed from the REACTCR MODE switch in any reactor mode position. Removal of the key locks the mode switch'in whatever mode was selected at the time the key is removed.
This allows the switch to be locked in the RUN position which may be undesireable.
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SHOREHAM NUCLEAR POWER STATION Control Room Ossign Revicw Audit Report s
- 5. DISPLAYS
ATEGORY FIPOING s
3 1.
Operators need visual indication on Panel 603 to verify that diesel generators are running.
2 2.
Control indicator lights for safety related system components indicate only that the command logic has been completed but do'not indicate actual component
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activstion or status.
2 3.* Glare on almost ell meter faces and chart recorder i
windows makes reading displays difficult and fatiguing.
1 4.
Meters that have positive and negative values within their ranges do not have a clear indications of.
positive / negative or lead / lag.
a.)
At least six meters have "+" markings in 1
both directions from the zero mark (meters 126A, 1268,127A,127B,100A,1083 for the drain tank levels),
b.)
Meters indicating reactive power for the diesel generators and the plant have no lead / lag or
+/- indications.
1 5.* Lettering of scales on MILLION LB/H1 LOOP A FLOW and MILLION LB/H1 LOOP S FLOW is too small and is difficult to read.
2 6.* Numerals for exporants on scales of counts per second meters for the SRM A, B, C, and D neutron detectors are too small to read from the center of the reactor operating console and are obscured from view of a standing reactor operator by the meter bezel.
2 7.* The meters for KILOAMPS AC M-G SET MOTORS A and B and for KILOAMPS AC GEPERATORS. A and B on Panel 602 are scaled in decimal notation which is undesireable.
2 8.* The HEATER LEVEL meters within the RFP Water Quality Recire Line have scales with negative values upscale and positive values downscale from the iero.
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SHOREHAM NUCLEAR POWER STAT 10N Control Room Design Review Audit Report
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- 5. DISPLAYS (Continued)
CATEGORY FIPOIrlG,
1 9.* Pressure indicators, MSIV Dutbd. Div 1; MSIV Inbd.
Div. 2; Main Steam Line A, B, C, D Lo Press; Steam Line Lo Pressure, have confusing scale labeling.
Positive pressure is measured in PSIG and vacuum is measured in inches of Hg.
The meter scales do not coincide with the scale pressure and vacuum range labels. A clear demarcation extending from the meter zero and between the pressure and vacuun scale labels would avoid confusion.
I
- 10. *The DEGRE F CLEANUP SYS TEMP meter on Panel 602 has scale numerals in blue. This is less readable and different from all other meter faces in the control room.
1
- 11. Weston meters have no units designated on the meter scale.
Instead, units appear on the meter label.
2
- 12. Several meters use non preferred scalegraduations such as PSIG REG HX INLET PRESS on Panel 602, and four meters for TRAVEL SCREEN AMPS on Panel MC8 are graduated in units of three, RE VENT CFN EXH AIR FLOW and R8 NGM VENT DEGREE F SUPPLY AIR TEMP in units of p
5 or 2.5.
Graduations of 3, 2.5, 7.5, 13, SO are not recommended.
2 13.
There are many instances of adjacent meters having different scales.
2
- 14. Several meters use nonlinear scales without operational justification.
These include Service Water Inlet flow on Panel 601 which is logarithmic and others such as Reactor Core Cooling Shutdown Head CLG and SVC Water Inlet Flow which have an expanded scale at high value.
2
- 15. Pointers on Weston Meters vary in size, shape, and contrast.
Contrast generally is.too lo.w.
This is due in part to construction dust within the meters and to l
the high levels of room illunination.
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SFOREHAM NUCLEAR POWER STATION Control Room Design R; view Audit Report h
- 5. DISPLAYS (Continued)
CATEGORY FIPOING,
- 16. Pointers on some Weston meters are reversed in pointer / scale orientation from the prevailing orientation used in the control room.
Examples of pointers reversed from the prevailing orientation include:
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KILOVOLTS AC, KILOAMPS AC, KILOAMPS AC M-G SET HOTOR, CRD P W AMPS, and RUNNING VOLTS on the diesel generators.
I 17.* Meters and recorders are not marked with normal operating limits, trip values, and alarm points.
1
- 18. Bottom indicator scale on Main Turbine Lubricating 011 Temperature controller is a valve position. On this t
scale 100; denotes 10CN CLOSED.
On all other valve indicators in the control room 100% denotes 10CN OPEN. All indicators in the plant should follow the same convention.
I 19.* Indicator lights on Panel 654 do not comform to the
- (
green-blue-red convention; they are in blue-green-red order.
3
- 20. Color-coded relay protection and open/ closed indicator lights for ACB12-13 and ACB11-10 are in different orders.
1 21.* The CRAC Isolation Valve Manual Override indicator lights have a white lens on the top indicator light and blue lens on the bottom. The lenses for indicator lights on adjacent systems are both white.
3 22.
Rod Display legend lights on Panel 603 are too small and too high for a 5th percentile operator to read rod designations and positions. Tall. operators find the high information density arrangement confusing.
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SFOREHAM NUCLEAR POWER STATION Control Room Design ReviGw Audit Report i
- 6. PANEL LAYOUT CATEGORY FDOING s
1 1.* There are two unused controls located on the Reactor Recirculation Benchboard (Panel 602).
3 2.
The irtoard and outboard Nuclear Steam Shutdown System control / display groups and the operationally related Nuclear Boiler Process control / display group are j
separated from each other by the Reactor Water Cleanup System, the Reactor Core Cooling Isolation System, and the Auto Depressurization System control / display groups.
This layout causes unnecessary operator movement between the NSSS and NBP controls and displays during some reactor operations 3
3.* The square root extractors are unnecessary equipment located on the vertical boards of Panels 601 and 602.
They have no control or display function.
3 4.
The Emergency Power Distribution System diesel generator control / display groups are not laid out in numerical or functional sequence.
1 5.
Insufficient demarcation is provided between C/D groups on Panels 601 and 602 that have different functions.
Example: Reactor Water Cleanup system and Reactor Recirculation system.
1 6.
Two sound powered phone jacks are located within the CO2 Purge System black demarcation box on the turbine Building and Miscellaneous Ventilation Panel (VCI). Jacks should have separate demarcation.
1 7.
Annuciator control buttons should have standard demarcation pads within the control room which clearly identify and separate them from other panel controls.
For example, the alarm control buttons for VCl and VC2 boards are within the demarcation of the turbine Building Air Exhaust System. Similar.Cpnditions exist at all alarm controls.
2 8.
Multiple systems on Panel MXP include mixed' sets of unrelated controls and displays that are not clearly segregated by layout or by lines of demarcation.
. 2 9.
Vacuum Priming Pump Controls A through D are located vertically on Panel MCS adjacent to unrelated controls which are laid out in a horizontal arrangement. No clear demarcation is provided between the two control arrangements..
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- 6. PANEL LAYOUT (Continued)
CATEGORY FI!OING s
3 10.
The Reactor Feedwater Pump Turbine controllers are on Panel 603 and are not integrated into the mimic of the RFPT system on the adjacent Panel MC8.
2
- 11. The operator has no way of determining Main Turbine Stop Valve and/or Control Valve positions while at the Main Control Boazd. The operator must go to Panel ECH to obtain this information.
2
- 12. Service Air Cbntrols (not yet labeled) are located on the Miscellaneous Control Panel (MXP). Associated meter displays are on the Main Control Board (MCB).
These controls are safety related and should be on MCB.
2
- 13. Unlabeled controls and displays for turbine building Service Water are located on the Miscellaneous Control Panel (MXP).
They should be located with the rest of the Reactor Building Service Water System C/D on the Main Control Board (MC8).
3
- 14. Reactor Building Standby Ventilation System (RBSYS)
Chiller Inoperative Alarm Controls are located on the i,
Turbine Building Air Exhaust Panel which is 10-12 feet from the RBSYS panel and RBSYS annunciator panel A2.
3
- 15. The spring loaded RESET control switch for RBSVS is located high on the VC2 board and must be held down while the operator moves other controls located much lower on the panel and offset to the left and right.
This is unreasonably awkward.
2 16.* On the Hydrogen Recombioner Psnel, the Leeds and Northrup recorders are too low to read easily.
I 2
- 17. On Panel ACH, meters are more than 70 inches above floor level.
3 18.* Top row of chart recorders on HVAC Board (over IT47 and IM50) and two meters are too high to be read easily. Poor readability is compounded by, glare.
I 2
- 19. The annunciators for NSSS A/B Isolation and NSSS C/D Isolation read logically from left to right although j
they are on different annunciator panels.
The associated Manual Isolation control buttons are arranged in left to right sequence CDAB.
2
- 20. Containment Purge Control Valv's 38 C and D are e
reversed with respect to their depiction on the mimic above. --.
SFOREHAM NUCLEAR POWER STATION Control Room Design ReviGw Audit Report 5,
- 6. PANS. LAYOUT (Continued)
CATEGORY FIFOING s
2 21.
Reactor Building Closed Locp Cooling Water Pump ABC and Service Water Pump ABCD control sequences are not in starAard sequential order.
1
- 22. On the Reactor Recirculation System mimic on Panel 602, the mimic flow paths for Recirculation Loop A and Recirculation Loop B are not the same. On A the flow path line passes through the flow control, on B it passes through it's % speed and % speed demand meter displays.
3 23.
- Two strings of six meters each are grouped on the HVAC Board for Air Cbnditioning System IX41. There should be no more than five in one string.
2 24.
The Primary Containment Atmosphere Cbntrol (ACH) Panel layout is poor. Arrangement is mirror image with some controls on the panel not mirror imaged. thits are in BA order from left to right. Switches IEII
- MOV 057 A and IEII
- MOV 057 B are interchanged and therefore located incorrectly on the mimic.
Temporary labels are used on the switches.
2 25.
On the Reactor Control Benchboard (Panel 603) the IRM range switches are mirror imaged on either side of the rod control.
The left to ri ACEG - rod controls - HFDB. ght order is 2
26.
Transfer switch MST 1138 and related switch MG 1138 are separated by switch 112 and a breaker. Similar arrangements. are found for switch 111 and switches 113A.
2 27.
On the Main Control Board (MCB) mirror imaging is used inconsistently outside of the Reactor Feedwater System mimic. Within the mimic the mirror imagery is consistent.
2 28.
Inconsistent use of mirror image 'layo0t'and parallel side by sidce layouts are used in the mimic of the Reactor Recirculation System on Panel 602. The Recircula~ tion Punp Suction Valves and Generator Drive Motors are arranged in a mirror image layout. The Recirculation Flow controllers and displays, and M/G Generator, Recirculation Pump Discharge, Pump Differential Pressure, and Jet Punp Flow dit, plays are in parallel side-by-side arrangement.
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SKyEHAM NUCLEAR POWER STATION Control Room 0; sign R:: view Audit Report 5
- 6. PANEL LAYOUT (Continued)
CATEGORY FIPOING s
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.2
- 29. The Reactor Water Level display located on Panel 602 near the RCIC systea has a 0 - 400 inches range.
If the water level falls below the zero reference level on this display, as it could during a loss of feedwater, the operator must go to the Wide Range Water Level meter on Panel 603 to determine the water level in the reactor.
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SHOREHAM NUCLEAR POWER STATION Control Room Design Revicw Audit Report t
- 7. CONTROL / DISPLAY INTEGRATION h
LATEGORY SIPOING s
2 1.
On Pii.'el 603 the SRM A,B,C, and D displays are located too far from the Rod Pull controls for easy readability.
3 2.
The computer printer outputs are too far from the computer console to be read easily.
3 3.
On Panels 601 and 602, the Rosemont SRV pressure indicators are too far from the SRV auto-depressurization controls to be read.
2 4.
On Panel 603 the " Withdraw" or " Continuous Withdraw" pushbuttons are located too far from the SRM counts /second and period meters and SRM recorders.
2 5.
Controls related to annunciators on annunciator panel.
"E" on Panel MC8 are located remotely on Panel MXP.
3 6.
The Safety Valve Temperature Indicator / Recorder, which provides positive indications of open safety relief valves, is on a back-panel behind Panel 601.
2 7.
The safety relief valves located on Panel 602 have corresponding annunciator tiles located remotely on annunciator panel G on Panel MCS.
2 8.
The controls located under Panel MCS annunciator panel 209-H relate to annunciators located remotely on amunciator panels 209-C and 209-0.
2 9.
The Seal Water Punp controls on Panel MC8 relate to annunciators located remotely en annunciator panels 209-A and 209-8.
2 10.
The controls for by-pass valves on Panel MC8 under annunciator panel 209-B relate to remotely located valve position indicators under annunciator panel 209-F. Separate indicator lights for the by-pass valve controls are needed either'above the EHC panel or below the feedwater and condensate mimic.
2 11.* Some annunciators are separated too far from reactor system controls associated with the annunciator and are not readable from the control location.
Examples: Condensate controls, Automatic depressurization system safety relief valve controls, f~
A _..... _. _.
SHOREHAM NUCLEAR POWER STATION Control Room 0; sign Revieu Audit Report 5
- 7. CDNTROL/ DISPLAY INTEGRATION (Continued)
CATEGORY FIWING s
2
- 12. Some annunciators are separated too far from their.
annuciator response controls and are difficult to read from the annunciator control location.
2
~
- 13. On Panel 603 the arrangement of selector controls and recorder displays for the IRM/RBM/APRM 2 pen recorders is confusing and does not show which rod block monitor is selected.
I
- 14. The Feedwater Turbine Test group on Panel MCB contains control shapes and colors which are inconsistent with corresponding indicators.
1
- 15. On Panel 602 there l's an inconsistent relationship among the valve switches and the corresponding indicator lights in both position and orientation.
2 16.
On Panel 654 the relationships betwesn switches and indicators is confusing. The left switch corresponds to_the bottom light and the right switch corresponds to the top light.
2
- 17. On Panel 603, the IRM bypass switch handles (G, A,C,&E), the AFRM switch handles (A,C,E) and the flow unit switch handles (A,C) are not easily correlated with the displays selected.
3 18.
Reactor Building Supply Fans which are given a vertical portrayal on the mimic (A aoove B) are associated uith controls (IT41-FN002A and IT41-FN0028) arranged horizontally reading in BA order from left to right.
2
- 19. On Panel 604, the relationship between the reset selector positions and the upscale and downscale trip indicators is not clear.
4 SHOREHAM NUCLEAR POWER STATION Control Room Design Review Audit Report i
- 8. LABELS APO LOCATION AIDS CATEGORY FIFOING s
1' l.
S.~-
.abels are located below the controls tt. > identify.
Exi g le: Panel ACH - Primary Containment Gas Analyzer Cbntrol.
1 Ihroughout the control room, display labels are nr.t consistently located either above or below the displays they identify.
~
l 3.
Labels on panel below recorders that protrude from the panel are hidden from view of standing operators.
Example: MXP Panel and Panel 603 1
4.
Label on reactor water cleanup return J-switch that states TO REACTOR VESSEL is misleading since the return flow path is through HPIC, RCIC, and feedwater lines to reach the reactor vessel.
1 5.
Temporary labels are used presently at various i
locations in the control room.
1 6.
Some labels are detached or not mounted ~ securely.
,I 1
7.* The labels on the Gai-Tronics alarm control at the operators desk identify the type of sound associated with each switch but they do not show what emergency j
conditions are associated with each switch.
2 8.
There are no instruction labels for operation of the centrol transfer switches on the remote shutdown panel.
l 1
9.
Labels are inconsistent in the formats of component identifiers and there is no distiction between the letter "0" and the nuneral zero when they are used in I
alpha-numeric identifiers.
1
- 10. Different abbreviations are used for the same word.
The egntrol room abbreviation list shows two and three different abbreviations for each of approximately 16 words.
1
- 11. The label on a display that has two indicators identifies the indicators as sensors at locations 1 and 2 but does not identify the actual locations of the sensors being read.
Example: Panel VC2 - Containment and Drywell Moisture Recorder.
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l
- 12. Switch positions are not clearly labeled on sc.a switches.
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SK)REHAM NTLEAR POWER STATION Control Room Design R; view Audit Report
\\.
t
- 8. LABELS AND LOCATION AIDS (Continued),
CATEGORY FIPOING 1
13.+ control positions of rotary switches are not adequately labeled to identify the function associated with each switch position.
I
- 14. Some labels do not adequately identify the function of the associated control or display.
Examples: Panel ACH - Anber light labeled C01440N ALARM.
Panels A2A and A28 - Pushbuttons labelled TEST.
I
- 15. Some annunciator labels are misleading.
Example: Tile 0403 - 125 NDC BUS Al BRKR OC TRIP on Annunciator Panel 210A.
I
- 16. Lettering has been rubbed off of sane labels.
I 17.* Use of white lettering on black background for labels is less desireable than use of black lettering on white tekground for the lighting conditions present in the cr.ntrol room.
1
- 18. There is no sign on the outside of the room housing the Remote Shutdown Panel that identifies it.
1 19.
There are unlabeled rotary switches at several locations.
1
- 20. The flow transmitter FT-002 scale is incorrecQ marked.
It reads 0-12 CFM but actually denotas 0-1200 CFM.
1
- 21. Scales on Feedwater Level Control (LIC 10) are not labeled.
1
- 22. Labels of displays do not clearly identify ~ the variables displayed, the units displayed, and the scaling parameters of the display.s.
1
- 23. On Panel 603, lines of denarcation do not separate the related sets of selector switches and recorders.
1
- 24. The CRT display control pus %uttons on the Panel 603 l
Reactor Operator's Console are not demarcated from other controls or labeled by function.
3 25.
On Reactor Building vent and Offgas displays on Panel 604 there is an inconsistent relationship between color coding of push buttons and meter scales.
SFOREHAM NUCLEAR POWER STATION Control Room Design Review Audit Report
\\
i
- 8. LABELS AND LOCATION AIDS (Continued),
- (
CATEGORY FIFOING,
2
- 26. Color coding of controls, position indicators, meter displays, recorder displays, Ci.T displays, mimics, and demarcation lines are not consistent throughout the control room.
3
- 27. The color code labeling scheme of meter ranges and selector switch positions of the Off-Gas Radiation Monitor on Panel 604 is confusing and use of x1 and x.316 scale multipliers make interpretation difficult.
2 28.
The use of red / black color coding to denote the alternate ranges for each pen of the 2 pen IRM/RBM/APRM reccrders and to correlate the color of each recorder pen trace with its associated range l
selector control is confusing.
1 2
- 29. On Panel 603 the color coding af Rod Drift, Rod MotionOverrlde,RCDSStatus,RIPSStatus,RodMotion Blocks, and Rod Insert and Withdraw Pushbuttons are not correlated with other controls and displays.
1 30.
Scme panels, controls. displays, and components of mimics are not labeled.
f.
l 2
- 31. Use of different shades of the same color on mimics is confusing.
Example: Remote shutdown panel and Panel 601.
1
- 31. Mimic labels and labels for corresponding controls or displays do not use the same identification nomenclature.
Example: Panels VC1 and VC2 l
1 32.* Mimics do not have arrows indicating direction of flow.
(
2
- 33. Convoluted flow path of Reactor Water Cleanup System
-~
mimic detracts from its usefulness.
f 1
- 34. On Panel 602, the flow mimic showing pump suction valves B-31-F023A, MOV031A and MOV0318 is inconsistent l
and confusing.
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SFOREHAM NUCLEAR POWER STATION Control Room DGsign Revlea Audit Report f
- 9. COMPUTERS AND CRT DISPLAYS CATEGORY FIbOING s
1 1.
Addresses of analog data points are indexed by system only. A cross reference index by point name and point alpha-numeric address code is needed.
2 2.
Excessive referencing of printed docunentation located at the computer control console is needed to interpret CRT displays.
Infomation needed to interpret each CRT display should be an intergral part of the display.
2 3.* There is excessive reflected glare from ceiling lights on the CRT video displays on Panel 603.
2 4.* The video display brightness contrast between the signal and background is not sufficient on the Alarm CRT.
2 5.
It is difficult to read CRT video displays on Panel 603 from the operator's desk and the computer control console which are located more than 12 feet away from the displays.
2 6.'
The reactor operator has no control.to selectively limit the amount of information being displayed on CRT displays. This lack of information control options can result in possible information overload for the operator.
2 7.
Panel 603 CRTs are mounted with the bottom of the screen 69 inches above floor level making it difficult to read the upper portion of the displays.
Recommended maximum mounting height is 61 inches.
2 8.
The location and orientation of the CRT displays on Panel 603 combined with the curvature of the CRT screens make it impossible to read the upper edge and far edge portions of the CRT displays from the operator's position at the center of the reactor console.
1 9.
The wording used to identify alarms displayed by be computer and the wording used on annunciator tiles differ for the same alarm. conditions.
4 Example: Annunciator - CRD HYDRAULICS TEW HI Computer - CONTROL RCD DRIVE TEMP ALARM 2
10.
There is inconsistent use of color conventions between the CRT displays and conventional control board and annunciator displays.
~ '
2 11.
Unconventional symbols are used on the CRT displays..
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SFOREHAM NUCLEAR POWER STATION Control Room Design Review Audit Report i
- 9. COMPUTERS AND CRT 'ISPLAYS (Continued)
D CATEGORY FImING s
2 12.
There is inconsistent use of color coding between different computer generated CRT displays.
I 13.
It is difficult to read printer printouts of decimal data because decimal points are not aligned on the printouts.
2
- 14. Some annunciator alarms for auxiliary systems are not shown by the computer alarm display.
2 15.
The alarm printer print speed, (30 characters per second)is too slow to provide timely orintouts when a large number of alarms occur simutaneously or in rapid succession. The recommended minimum printer speed is 300 lines per minute, (200 characters per second at 40 characters per line).
2 16.
Use of flashing yellow 99.9 to indicate that data should be ignored is confusi(q.
2 18 The computer. generated digital displays and trend recorder. displays on Panel 602 do not have any identification of the variables being displayed.
[,
2 17 The ccmputer generated CRT display system does not have prompting or structuring features to assist the operator request additional or corrected information.
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SHOREHAM NUCLEAR POWER STATION Control Room Design Review Audit Report s
~
- 10. DATA RECORDIE NO RETRIEVAL CATEGORY FIM)ING s
2 1.
Combined use of red and black to distinguish between the high and low range scales and to identify the two pen traces of the IRM, APRM, and RBH recorders is confusing.
3 2.
The 12 channels of data displayed on the. turbine vibrstion multipoint recorders on Panel MCB are difficult to read because:
a.) The sensor identification nmbers are too
- small, b.) the color coding of the printed data points is not distinct, c.) the chart is arranged in a three column format without Gliniation between the parallel columns, and d.) the sensor channels displayed in each column are not consistently grouped in nmerical order.
1 3.
Strip chart recorders are loaded with chart paper having scales that do not match the recorder scales.
2 4.
Multipoint recorders have an excessive number of sensor channels displayed on a single chart, (up to 12 channels per chart).
~
1 5.
It is d1/ficult to distinguish between the blue and 1
green traces of some recorders.
1 6.
Full scale deflections of the IRM and APRM 0-125 an.d 0-40 ranges do not match.
The difference between the full scale deflections is nearly 1/4 inch.
The recorder chart paper is printed with the two scales alternating every 1.5 inches. A single 0-100 scale for all ranges would be satisfactory for operator use since absolute values of the neutron production rate l
or power rate are not used by the operators.
i 1
7.
Units associated with recorder scales are not l
identifLeo.
-~
not shown on recorder scales.g values or rhfiges are 1
8.
Setpoints and normal operatin 1
9.
Most chart recorders are not operational and could not be evaluated completely.
(
l
- 10. Data recording and retrieval could not be evaluated because the procedures are not' fully operational.
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