ML20039H204
| ML20039H204 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 12/08/1981 |
| From: | Moore V Office of Nuclear Reactor Regulation |
| To: | John Miller Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8201190716 | |
| Download: ML20039H204 (42) | |
Text
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'o UNITED STATES ~
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g NUCLEAR REGULATORY COMMISSION i
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DEC 8 1981 MEMORANDUM FOR:
James R. Miller, Chief, Standardization and Special Projects Branch, Division of Licensing FROM:
Voss A. Moore, Chief, Human Factors Engineering Branch,'
Division of Human Factors Safety
SUBJECT:
CONTROL ROOM DESIGN REVIEW / AUDIT REPORT, CLINTON POWER STATION, UNIT 1 Please transmit the attached Human Factors Engineering Control Room Design Review / Audit Report for Clinton Power Station, Unit 1, to Illinois Power Company for their review and comment.
Inform the applicant to contact us as soon as possible if it has any questions regarding the report. Also, we request that you arrange for a meeting in Bethesda with the applicant on January 5, 1981, to discuss its proposal to correct deficiencies identified in the attached report and the schedules for implementing its corrective actions.
This report is based on a review of the applicant's Preliminary Design Ass'ss-e ment and the design review information provided by the Human Factors Engineer-ing Branch team and consultants that conducted the Clinton Power Station control room design review / audit. The team members included the following:
A. M. Ramey-Smith (team leader), R. G. Ramirez, and D. I. Serig of the NRC; and our censultants L. R. Peterson and J. W. Moore from Lawrence Livermore National Laboratory, and G. Smith and B. Paramore from Biotechnology, Inc.
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w Voss A. Moore, Chief Human Factors Engineering Branch Division of Human Factors Safety
Attachment:
Clinton Power Station Control Room Design Review / Audit
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CONTACT-E DEC291981 > [
i A. M. Ramey-Smith
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J. Kramer DHFS Branch Chiefs D. Tondi S. Weiss J. Williams, DL R. Peterson, LLNL G. Smith, BTI H. Livermore (R-I)
HFEB Members 9
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AUDIT REPORT Human Factors Engineering Control Room Design Review / Audit Clinton Nuclear Power Plant Unit No. 1 Illinois Power Company December 3,1981 A three day human f actors engineering control room design review / audit of the Clinton Nuclear Power Plant, Unit 1, control room was performed at the site on November 3 through November 5, 1981. This design review was car'ried out by an audit team from the Nuclear Regulatory Commission, Di' vision of Human Factors Safety, Human Factors Engineering Branch.
This report was prepared on the basis of the HFEB's review of the applicant's preliminary design assessment and the human f actors engineering design review / audit performed at the site.
The review team included human f actors consultants from BioTecnnology, Inc.,
Falls Church, Virginia, and from Lawrence Livermore National Laboratory (University of California), Livennore, California.
The sections in each part of this audit report are organized and numbered to.
conform to the guidelines of NUREG-0700.
They summarize the audit tefm's observations of the control room design and layout, and of the control room operators' interface with the control room environment.
Some discrepancies which were dccumentec in the Preliminary Human Factors Review of the Clinton Control Room made by General Physics Corporation and submitted to the NRC Human. Factors Engineering Branch by Illinois Power Company as their preliminary design assessment (PDA).
The PDA findings were reviewed by the NRC audit team. PDA findings that the NRC audit team verified to be discrepancies are listed in Part A of this audit report.
The PDA findings' that the audit team did not consider to-be human engineering discrepancies are listed in Part B.
Human engineering discrepancies observed by the NRC audit team in addition to the PDA discrepancies are listed in Part C of this audit report. A list of those items that the NRC audit team could not evaluate is presented in Section C-10 of Part C.
The condition of construction or installation of these items at the time of the site visit was not sufficiently finalized to permit review. ~
t f
Audit Report.
Clinton 1 Observed human factors design discrepancies are 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.
Priority rating 1 and 2 discrepancies should be corrected prior to issuance of an operating license.
Priority rating 3 discrepancies should be evaluated and proposed actions reported as part of the long term design review that will be required using the detailed design review guidance provided in NUR{G-0700.
Note that some priority ratings include a superscript one (e.g., 3 ).
Since the resolutions of these discrepancies involve simple corrective act' ions relative to the potential for improving operator performance, these discrepancies should be corrected prior to issuance of an operating license.
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AUDIT REPORT
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Part A Human Factors Engineering Control Room Design Review / Audit Clinton Nuclear Power Plant Unit No. 1 Illinois Power Company A-1. CONTROL ROOM WORKSPACE PRIORITY FINDING I
3 1.
Passageways between P800, P801 and P870, P877 respectively are 26" wide; passageways between P680 and P601, P870- respectively are 27" wide.
(10.2)
I 2.
Access to the Remote Shutdown Panel is not currently limited.
(10.1) 3 3.
The standing operator cannot see annunciator tiles on P680 inserts 12, 05 & 06.
(3.6)
.c 3
4 Meters on C61-P001 are too high to be read by the average op e rat or.
They are about 6' from the floor.
(3.46) 3 5.
Some labels on C61-P001 are too high or too low to be read.
(3.49) i 6.
The shiny surf ace of control pushQuttons and CR2 40 switches results in glare (9.5:2.6 against panel background).
(2.7) 1 7.
The keyboard f or the PMS System on P680 has significant glare which obscures the legends.
(3.3) l 1
8.
The minimum reading distance for meters should be 7 feet.
The glare problem makes this difficult.
(3.57) 1 9.
Significant glare is occurring on all meters in the control room.
(3.56)
A-1 t
Clinton 1 Audit Report Part A A-3. ANNUNCIATORS PRIORITY FINDING 1
1.
Presently there is no "first-out" indication other than the alarm print-out.
(6.11) 3 2.
In section 20 on P601, nothing in this section is related to the "High Temp Tubr Bldg Mn Stm Line Div 1,-2, 3 & 4" alarms.
(6.7) 3 3.
In section 22 on P601, some alarms for the floor drains are above the CRD controls and some CRD alarms are above the floor drains.
(6.9) 3 4.
In Insert 07 on P680, the " SCRAM DIS VOLUME NOT DRAINED" is all alone, and not grouped with its related tiles.
(6.3) 1 3
5.
In section 56 on P870, the " Loss of Instrument Air ADS Relief Vivs" alarm appears to be-out of place.
(6.4) l l
c 3
6.
The arrange.?ent of tiles within windows on either side of the full core dis-lay on P680 is not consistent between the two windows.
(6.2) 3 7.
In section 18 and 19 on P601, annunciator tiles are not arranged the same across divisions, (e.g., LOW-LOW SETPT DIV 1 SEALED-IN).
(6.8) 3 8.
Annunciators are used which give nonspecific information, (e.g., "High/ Low Temp RCIC Pump Room").
(6.12) 2 9.
Annunciator acknowledge, silence, test, and reset buttons are large, grey, and flat surface on some panels; and large, silver and recessed on other panels.
(2.5) 2 10.
The annunciator panel on P801 for the B system is missing the
" Trouble VD System Local lPL55J".
(6.5) 1 11.
In section 21 on P601 " CST Water Level Low" is a misnomer, it should be RCIC tank.
(6.6)
A-2
Clinton 1 l 7-~
Audit Report l
i Part A A-4. CONTROLS PRIORITY FINDING I
3 1.
The use of the RHR B Shutdown Cooling Suction Valve lEll-F006B was not apparent to operators. Remote Shutdown Panel.
(4.24) 1 2.
The*e is little use of knob-coding on the remote shutdown pane'.
(4.25) 2 3.
There is not d'istinctive shape or color coding,0f controls for throttleable valves.
(2.6) 1 4.
Some pushbuttons light up when depressed. However, not all of these have lamp test capability.
(3.53) 1 5.
An administrative control should be employed for key lock controls on P801 and other panels including storage of keys.
(3.38) 1 6.
On P601 insert 16, the " Norm" j-handle position on the=HPCS WATER LEG PUMP is ambiguous.
(2.3) 1 7.
On P601 insert 17, the " Neutral" j-handle position is amoiguous.
(2.4) 2 8.
Throttle valves on P601 are hara to hold open for periods of
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time.
(2.2) 6 A-3 1
I
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Clinton 1 l _.
Audit Report Part A I
A-5. DISPLAYS PRIORITY fit! DING 1
1.
The informational transilluminated displays on the upper right of each section on P801 are missing some tiles.
(4.15) 2 2.
On P870 insert 52, the 6900 V Bus 1B Voltage scale is limited to 5250.
(3.7) 3' 3.
The meters for' the LP HTR's on P870 read as fo,llows:
2A, 28 -10 to 10 3A, 38 -10 to 10 4A, 48 -10 to 10 SA, SB -7.5 to 7.5 (3.8)
I 3
4.
On P870 decimal fractions are used on the scales for the following meters:
UAT 1A FDR TO 4160 BUS 1A WATTS l
BUS 1RT4 FDR to 4160 BUS 1A WATTS BUS 1RT4 FDR TO 4160 BUS 1B WATTS UAT 1B FDR TO 4160 BUS 1B WATTS '
.c (3.10) l 1
5.
On P678 servo current meters of the STM BYPASS PRESS REG SYSTEM is in % from 0-1100.
(3.26) 2 6.
The meter for DGB Output Watts for diesel generator output on P601 is scaled to 27.5 Kilowatts.
(3.27}
2 7.
The DGlA & IB OUTPUT WATTS meter on P877 has a scale reading from 0 to 27.50 with increments at 4.58, 9.17, 13.75, 18.33 and 22.92.
(3.33) 1 1
8.
The OS AIR TEMP RAD MON DIV 2 RAD LVL Meter on P800 has a scale reading.01 at the bottom with zero above it and increments of 10 to 100 above the zero.
This also applied to DIV 1.
(3.42) 1 9.
Suppression pool level meter on C61-P001 has a scale ranging from -24 inches to +6 inches. This scale is not consistent with similar control room indication, and reference point is unclear.
(3.52)
A-4
,._.,,.-mm__,
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Clir; ton 1 Audit Report Part A A-5. DISPLAYS (Continued)
PRIORITY SINDING 2
- 10. On the Reactor Water Level Recorder on P678, the scales appear incorrect for Wide Range values.
(3.20)
I 11.
The scale for JET PUPP FLOW on the JET PUMP FLOW / CORE PLATE DP Recorder on P678 is not high enough for the-operating parameters.
(3.21) 2
- 12. On P601 insert 18, the Suppression Pool Level chart recoroer is scaled in inches (0-80) while the procedures reference SP level in feet.
(3.32) 2
- 13. The scale on the COND BSTR PUMP DISCH HDR PRESSURE on P870 has a range reading from 0 to 200 (Insert #57) which is an inadequate range for operation.
(3.15) 1 14.
Steam Flow /Feedwater Flow scales on P678 show a range that is too small for the actual operating values.
(3.19)
.c 1
15.
The CCW PUMPS 1 A,1B, IC Current meters on P801 should not show negative values.
(3.39) 1 16.
Readability of instrumentation on P678 from the P680 position is difficul.t without the assistance of bariding (i.e., at 120" letter height would have to De.48" to be read, no labels or scale numbers are larger than.25").
(3.17)
I 3
17.
MAIN STOP VALVE POSITION GROUP MILLIAMP METERS on P678 have a scale from 20 to 0 to 20. Positive and negative indications are not shown.
(3.22) 2
- 18. One indicator needle on the steam control valve on the Turbine control panel, P680, is very small, and difficult to see.
(3.1) 3
- 19. White indicator needles are used against a black background on meters.
(3.54) 1 20.
Tolerance zones are not indicated on most meters in the control room.
(3.55)
A-5
Clinton 1 Audit Report
< ~
Part A A-5. DISPLAYS (Continued)
PRIORITY F.IN DING 1
21.
There should be scme way to positi,aly diagnose a failed indicatin light.
Currently there is na lamp test capability to do so.g (3.58) 1
- 22. Recorders are not always clearly marked with type of paper required.
They should also provide appropriate chart paper.
(3.59)
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A-6 l
l
4 Clinton 1
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Audit Report Part A A-6. LABELS AND LOCATION AIDS PRIORITY FINDING 1
1.
Computer controls for OUTPUT SOURCE on P680 panel are mislabeled. AUT0/ MANUAL should be' SELECT 1/ SELECT 2 and MODE should be AUT0/ MANUAL.
(3.5) 1 2.
Review of a new label list for Remote ShutdQwn found significant improvements.
(5.15) 3I 3.
The chart recorder for REACTOR WATER CLEANUP SYSTEM RWCU/RECIRC CONDUCTIVITY on P678 has a label reading "R - Red" and "R -
Blue".
(3.18) 2 4.
COMBINED INTERMEDIATE VLV POSITION meters on P678 are not labeled.
(3.23) 2 5.
GEN MEGAWATTS Meter on P678 is not labeled.
(3.25) i 2
6.
The meters on the RCIC Section on P601 are not labelede (3.28) 2 7.
The switches on Westronics DW RTRN AIR / AREA TEMP Meter on P800 are not labeled.
The same is true for the ECCS Pump RMS Temp Meter.
(3.43) 1 8.
... ;n ;. ' ;f the discharge pressure meters on P601
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insert 21 are unlabeled.
(4.11) 1 9.
Tags are too large and tend to obscure adjacent indications.
(9.1) i l
- 10. The IRM insert and withdraw pushbuttons on P680 are not labeled l
(Insert 06).
(4.1) 1
- 11. RHR A Head Spray Flow on P601 is labeled incorrectly.
(4.13 )
1 12.
Test buttons for the Scram Discharge Volume Drain Valves on P680 are not labeled so (Insert 06).
(5.1)
A-7
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Clinton 1
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Audit Report
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Part A A-6. LABELS AND LOCATION AIDS (Continued)
PRIORITY EINDING 1
- 13. Many controls on P680 are as yet unlabeled, as examples, the exciter breaker in the generator section, and the standby pump selector joystick.
(5.2) 1 14.
The Reactor Protection System Bypass keylock switches on P680 are mislabeled.
(5.4)
A i
- 15. Reactor water level on P678 is a two-channel reorder but is only labeled for one channel.
(5.5)
^
l
(5.6) 1
- 17. On P870 insert 55, several switches are unlabeled.
(5.7)
~
1
- 18. On P870 insert 56, one switch is unlabeled.
(5.8) c 1
- 19. On P870 insert 59, a button on the bottom right is unlabeled.
(5.9) 1
- 20. On P601 insert 19, the indicator lights for safety relief valve solenoid "B" activation are unlabeled.
(5.10) 1
- 21. On P601 insert 21, a bank of meters on the lef t is unlabeled.
(5.11) 1-
- 22. Labels on P801 are not used to functionally group controls and displays.
(3.51) 2
- 23. There is no hierachical labeling scheme to aid operators in identification of systems and subsystems.
(5.19) or' 2
- 24. Controls and components of similar of' common function on P870 are not visually distinguishable by heirarchical labeling.
(3.14)
A-8 l
Clinton 1 Audit Report Part A
+
A-6. LABELS AND LOCATION AIDS (Continued)
PRIORITY FINDING 2
- 25. Functional groups are not indicated on each panel.
(4.28) 2
- 26. Labels on the MAIN STOP VLV. POSITION / COMBINED INTEREDIATE VLV POSITION SECTION on P678 are placed above the displays.
(3.24)
I 3
- 27. Labels are pla,ced below the trip buttons on P680.
(5.3)
I 3
- 28. Labels placed below recorders on C61-P001 are sometimes eclipsed by the recorder itself.
(5.17)
I 3
29.
Indicator lights on P800 obscure the first line of print on many indicator light labels because the lights are cut into t'he labels themselves, directly above the characters.
(3.40) 2 30.
Division indication on all labels is too small to be seen without close scrutiny.
(4.29)
C 2
31.
Division numbers on labels for C61-P001 are very small and difficult to read.
(5.16) 2
- 32. Labels are written inconsistently for the SGTS UPSM & ONSM HEPA FILT for th5 A and B sections on P801.
(5.12) 1 33.
The test switch for CGCS TEST on P300 is labeled " TEST" for division 1 and "INOP" for division 2.
(5.13) 3I
- 34. Some abbreviations used on labels on C61-P001 are inconsistent. For example, shutdown service is abbreviated SX and SSW on remote shutdown and control room panels.
(5.18)
I 3
- 35. MS TO SJAE lA INLT VLV ICA01AA in Aux and Extraction Steam Section on P870 is not labeled as to direction of operation.
(3.11) 1
- 36. Labels on C61-P001 are black on yellow and white on blue.
'(3.48)
A-9 I
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Clinton 1 Audit P.eport Part A A-6. LABELS AND LOCATION AIDS (Continued)
PRIORITY FINDING 1
- 37. Labels on the remote shutdown panel are black on yellow and other colors.
Labels are also temporary.
(5.14) l 1
- 38. Font width on labels varies significantly from label to label on C61-P001. Some are very thick and cannot be read easily.
(3.50)
I 3
- 39. Mimics on P601 are incomplete.
(3.31) 3I
- 40. Mimics are incomplete. This is due to the unfinished state of the board and because some mimic pieces have become detached.
Also, not all mimics make use of arrows when they could be helpful to operators.
(5.20)
.i 3
- 41. Brown mimic lines may not provide sufficient contrast with black background on P870.
The luminance ratio is 3.20:1.64 against the black panel background.
(3.12 )
,e 2
- 42. Mimic line color coding is usually consistent within systems.
In the steam / water systems:
Red - Steam Green - Service (lake) water Yellow - Condensed steam Blue - Purified water Orange - Extraction steam Brown - Condensate piping White - Gland sealing steam Grey - Non-condensable gas vent to suppression pool from RHR heat exchanger (5.21)
I 3
43.
Some flow indication arrows on the mimic P680 are " cut off" and, therefore, not clear in their indication.
(3.4)
'3I 44.
Some flow direction indications are not present on mimic lines and some mimics are not complete on P801.
(3.37)
A-10 1
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Clinton 1 Audit Report Part A A-6. LABELS AND LOCATION AIDS (Continued)
PRIORITY FINDING I
3 45.
On 0500 incert 52 has no flow direction indications on the mimic.
(3.44) 2 46.
Demarcation lines are not used to enclose relatad displays on P801.
(3.36) e A-11 O
i Clinton 1 Audit Report Part A A-7. PROCESS COMPUTERS f
PRIORITY FINDING 2
1.
A few display formats appear to be too dense in hardcopy. For example, Feedwater A display (3A), parameter listing on lef t of screen is extremely compact; and for the Turbine & Aux Sys Startup & Shutdown display (88), the mimic itself may be too dense.
(8.6) l, 3
2.
Scale incremen,ts on percentage bar graphs are confusing. For there are 25 graduation marks on the Beactor Water exampl e, System. Performance display (ld), and 16 and 11 marks Cleanup for scales on the Main Steam Press Reg Sys Performance (7J).
Since these scales are not otherwise marked, it is assumed they range from 0-100% of the instrument range.
(8.5)
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A-12
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Clinton 1 Audit Repcrt Part A A-8. PANEL LAYOUT PRIORITY F_INDING 2
1.
Area Radiation Monitor and Process Radiation Monitor cisplays on P680 have not yet been installed.
(4.2) 3 2.
Indication of shutdown cooling, such as reactor water temperature and drywell pressure, should be. considered for inclusion on the remote shutdown panel.
(4.23) 3I 3.
The Sump Discharge System is included on this section with the Control Rod Drive Hydraulics on P601.
(4.14) 1 4.
On PS00 insert 63, several systems are placed on the panel.
(4.19) 3 5.
The placement of the Turbine Testing panel in the control room is not optimal.
It requires two operators to test the turbine.
(4. 7 )
.c 1
6.
Meters in the top lef t bank on PS01 are not separated according to function. There are nine meters in this bank, which makes it more difficult to identify a given indicator.
(4.17) 1 7.
The Cont Bldg Exh Air Temp is grouped with six other, unrelated meters on P800.
(4.18) 1 I
1 8.
The Condenser A CW Inlet Temp meter on PC00 is not associated with other temperature readings.
(4.22) 3 9.
Division 1 Cross-Tie Valve switch on C61-P001 has indicator lights stacked above it.
Not all lights are associated with the switch.
(4.26)
I 3
10.
In the lower bank of meters on P601 the Diesel Generator C pancl, the three lef tmost BUS VOLTAGE meters have no relation to the other meters.
(4.10) 3I 11.
In the RHR sections on P601, the Containment Spray Delay Timer Reset switches are identical to the Containment Spray Manual Initiation switches and they are close proximity.
(4.12 )
y sn A-13
4 Clinton 1 Audit Report Part A A-8. PANEL LAYOUT (Continued)
PRIORITY F_INDING 1
- 12. The labels for the CGCS CMPR 1A and 18 meters on P800 indicate that the B meter is on the lef t and the A meter is on the right, contrary to convention in the control room. Presently it appears that these meters are criss-crossed with their controls below.
(4.21)
I 3
- 13. The CDSR LINE S GW INLET TEMP meter on P800 insert 63 is not arranged consistently with other nearby meters, (3.45) 3I
- 14. One group of 8 and one group of 7 meters on P601 are clustered together.
(3.29) 3I 15.
There is a group of 8 meters on C61-P001 grouped together.
(3.47) 31
- 16. One group of seven and two groups of nine meters on P800 are clustered together.
(3.41)
.c 1
17.
There are two groups of 9 meters each and two groups of 6 meters each on P801.
(3.34)
I 3
- 18. There are two groups of 9 and two groups of 6 meters located together on P870.
(3.9)
I 3
- 19. Meters are grouped in sets of 6 or more on P870, which may make it difficult to locate a desired reading.
For example, in the Aux and Extraction Steam section there is a bank of 9 meters.
(4.8) 2
- 20. On P800 insert 63, the CGCS SYS TEST switches are not mirror-imaged like the rest uT the switches there.
(4.20)
A-14 i
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Clinton 1 i:
Audit Report Part A 1,
I A-8. PANEL LAYOUT (Continued) 1 f
PRIORITY FINDING 2
- 21. Mirror imaging is used inconsistently in the Aux Power 4
Emergenefently between the A and B busses. Displays are c. ranged section on P870.
i inconsis The following arrangement of meters should be established to comply with the changes recommended for the Aux Power Section and to afford consistency between the A and B buses:
i A bus from left to right:
j 4160V BUS 1A Voltage 480 BUS, G.1, K & 0 Voltagt Battery IE Current DC MCCIE Voltage j
B bus lef t to right:
DC MCCIF Voltage
]
Battery IF Current l
480 V BUS H, J. I, & K 2
4160 V BUS 1B Voltage
]
(4.5) 1 2
22.
In addition to the above, the upper bank of meters in the Aux Pcwer Emergency Section on P870 is not fully mirror-imaged, and j
should be changed to comply with the changes in the Aur Power Section.
(4.6)
/
Mirror imagifing is used in the Auxiliary Power section on P870 2
23.
but its application is not consistent.
(4.4) k l'
A-15
Clinton 1 Audit Report Part A A-9. CONTROL / DISPLAY INTEGRATION PRIORITY FINDING I
1.
Meters on P601 are not optimally lined-up with controls on the
~
3 Diesel Generator C panel.
(4.9) 31 2.
The source of audibles for annunciators is presently in panel 9;' *
P680.
(6.10) n-g e
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e A-16 i
AUDli REPORT Part B l
Human Factors Engineering Control Room Design Review / Audit Clinton Nuclear Power Plant Unit No. 1 Illinois Power Company The following section contains a list of items from the PDA that were found not to be valid discrep.ancies.'
PDA ITEMS FOUND NOT TO BE VALID DISCREPANCIES B-3. ANNUNCIATORS FINDING 1.
One tile on P680 reads " Turbine RFP OFF".
The meaning of this alarm is unclear.
(6.1)
B-4. CONTROLS
-r FINDING l.
There are no pointers on the J-handles.
(2.8) e.
B-1 i
Clinton 1 Audit Report Part B PDA ITEMS FOUND NOT TO BE VALID DISCREPANCIES B-5. DISPL'kYS 1
FINDING 1.
Scales markings for GEN 1 OUTPUT POWER FACTOR on P680 have more than 9 minor marks between major numbered scale markings.
(3.2) 2.
The 480V BUS C,urrent Meters for 1G,1K, F & N TBCCW HW Outlet Press on P870 have 14 minor marks between numbered markings.
(3.16) 3.
Scale for RHR PUMP A AMPS meter on P601 has a scale with 14 minor markings between major numbered markings.
(3.30) 4 The following meters.cn P801 are incremented by 15.
The recommended increments are 1, 2, 5 or 10.
a)
DW CHILLER 1 A & IB INLET WATER TEMP b) CCU HX OUTLET HDR PRESS c) FUEL P0OL CLG PMPl A & IB CURRENT d) CDSR LINES A 7 B DIFF PRESS
-c e)
SERVICE AIR HDR PRESSURE f)
SERVICE AIR CMPR 0,1, & 2 CURRENT c) PLANT CHILLERS A, B, C, D, E 7 F CURRENT 13.35) 5.
The charts from a recorder should be marked periodically (at least once per shif t) with the date, time, and initials.
(3.60) i l
B-2 i
I Clinton 1 l' I Audit Report
]
Part B d
i
' PDA ITEMS FOUND NOT TO BE VALID DISCREPANCIES i-B-6. LABEL *S AND LOCATION AIDS e
FINDING j
l.
The Unit 1 plaque in the mimic for the switchyard on P870 is j
removed from the breaker arrangement.
(4.3)
I j
2.
Flow indicatio,n within mimic lines is not present on P870.
(3.13) l '
i B-7. PROCESS COMPUTERS I
, FINDING 1.
Dirt has accumulated on keys of keybcard for PMS on P680, cmaking them difficult to read.
(2.1) i
{
2.
Performance Monitoring System (PMS) CRT keyboard on P870 ir. sert 0
61 is at a 450 angle. A 25 slope is the maximum s-0 0
j allowaole, with 16 -17 preferred.
(8.1) l l,
3.
Response time for data acquisition is 250 milliseconds and for j.
data oisplay or retrieval is approxi.nately 1 second.
(8.3) i j
4.
CRT regeneration rate is 50 cycles per second.
(8.4)
~
l 5.
The Display Control System has dual processor capability.
This j
should preclude loss of parameter data, should a CRT fail, Since automatic recombination of the formatted output to j
remaining CRTs occurs.
(8.2)
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j-B-3
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Clinton 1 Audit Repor?
Part B PDA ITEM 5 FOUND NOT TO BE VALID DISCREPANCIES B-8. PANEL *" LAYOUT FINDING i
1.
In the top right bank of meters for both A and B systems on P801, the water and pressure indicators are.placed with other indicators.
(4.16)
B-9. CONTROL / DISPLAY INTEGRATION FINDING 1.
Reactor pressure and reactor level meters are not in close proximity to RCIC controls on C51-P001.
(4.27) o I
B-4 5
i AUDIT REPORT 1!
Part C 1:
i jv j
Human Factors Engineering
{
Control Room Design Review / Audit i
i e
Clinton fuelear Power Plant Unit No. 1 Illinois Power Company j
l j
C-1. CONTROL ROOM WORKSPACE PRIORITY FINDING i
2 1.
There is inadequate separation between the front surface of the Remote Shutdown Panel and the backpanel surf ace of the adjacent j
electrical panel.
The distance between the opposing surf aces is approximately 32 inches.
This is an inadequate amount of workspace for easy operation of the Remote Shutdown Panel by one or more operators.
The minimum recommended separation distance between a single row equipment panel and a wall or other opposing surf ace is 50 inches.
I 2
2.
The J-handle Transter Switches on the Remote Shutdown Panel are mounted too low.
They are located between approximately 20" and 33" above the floor.
This low control height makes j
them inconvenient to operate.
)
3 3.
The views of portions of the P800 Containment Isolation, Plant
]
Service Wat'er, and Spent Fuel panel and the P801 Secondary Containment and Standby Gas panel are obscured by P870 and P601 I
when viewed from the operators' position at the P680 Nuclenet i
control console.
i
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1 4.
There are no provisions for storage of procedures at the Remote Shutdown Panel.
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.C-1 l*
Clinton 1 Audit Report Part C C-3. /NNUNCIATORS PRIORITY NINDING 3
1.
No separate first out annunicator panel has been provided for the reactor system to identify initiating events that cause a reactor trip.
3 2.
The turbine-ge,nerator system does not have a separate first out annunicator pane:.
1 3.
None of the annunicator panels have a prioritization scheme to enable the operators to differentiate the most important alarms from less important ones.
~
2 4.
The audible signals to indicate cleared alarms on the annunicator system do not have a finite duration of activation. Manual operator action is required to silence the cleared alarm signal.
c I
3 5.
The vertical columns and horizontal rows of the annuhicator panels have not been labeled with easily visible alphanumerics to f acilitate visual location of each tile in a panel by its matrix coordinate designation.
2 6.
In case of an annunicator' flasher f ailure, flashing annunciator tiles do not necessarily illuminate and remain steadily illuminated af ter flasher f ailure occurs, 3l 7.
Annunciator tiles that must be ON for an extended period during normal operations are not distinctivily coded for positive recoginition of this condition during periods of normal operations.
I 8.
Some annunicator tile legends are confusing.
Example:
TRU BYPASS / DISAGREE DISABLE on P680 1
9.
On P601 and P680 some annunicator tile legends address more than one specific condition.
This causes uncertainty concerning the condition being alarmed.
Examples:
a.) SLC TANK LEVEL HIGH/ LOW b.) CAM DIV 1 SMPL PNL PWR LOSS /SMPL FLOW HI/LO C-2 l
i Clinton 1 j
Audit Report Part C C-3. ANNUNCIATORS (Continued) j I
PRIORITY NINDING 1
- 10. Abbreviations and acronyms are not' used consistently within th'e control room.
Some annunicator legends use abbreviations not contained on the list of standard abbreviations.
1 1
11.
Annunicator control pushbutton groups are not laid out w.ith the same arrangement of pushbuttons in the control group on all panels.
i 3I
- 12. The relative location of annunciator control pushbutton groups is not the same-from panel to panel.
l 1
- 13. The annunicator ACKNOWLEDGE pushbutton in the P805 annunciator control pushbutton group is not labeled to identify its function.
s 3
- 14. Annunicator controls recessed on the center of the P680 Nuclenet control console cannot be seen by a seated operator.
3 15.
The top two rows of annunciator tiles on the center annunciator 4
panels on P680 are not within view when an operator is standing.
3I
- 16. On P801 Annunciator Panel U the tiles labeled TROUBLE VX SYSTEM
~
i LOCAL PNL IPL65JA are duplicated in Division 1 and Division 2.
l The Division 2 annunciator tile sbould probaoly be for PNL IPL65JB.
2
- 17. There are no annunicators at the Remote Shutdown Panel for conditions that are annunciated in the Control Room.
Examples:
a.) Suppression Pool Temperature b.) Reactor Vessel Water Level r
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.C-3
Clinton 1 Audit Report Part C C-4. CONTROLS PRIORITY TINDING 3
1 The Square Root Extractor for RCIC Pump Flow located on P601-21 is an unnecessary instrument on the front panel that is not used by the operators.
I 2.
The pushbuttons on the Start Up Level Baile" controller on y
P680-03 are ha,rd.to depress because they are too small in diameter and are recessed too far.
1 3.
Controls are consistently located too close to the front edge of the benchboard throughout the control room.
Controls are approximately 13/4 inches from the edge of the protective rail and approximately 7/8 inch from the edge of the benchboard.
1 4.
Transfer switch J-handles on the Remote Shutdown Panel are vulnerable to inadvertent activatien.
The J-handles project approximately 4 inches into a workspace that is only 32 inches deep and they are located approximately at knee level.
c 1
5.
There are controls whose control movements do not conform with established direction of movement population stereotypes.
Example:
Main Steam Line D on P601-19 is OPEN/Lef t-CLOSE/Right according to its label.
3 6.
There does not appear to be any logical color coding of large pushbutton controls tt ougnout the Control room.
Example:
REPT 1B TURNING GEAR RESET on P870-59L I
7.
Several of the Bailey controllers in the control room appear to have the Manual and Automatic control positions reversed.
There is an inconsistency from control to control.
Examples:
l a.) RECIRC Loop A Flow Control on P680-04 b.
RECIRC Loop A Master C2ntrol on P680-04 c.
RECIRC Loop A Flux Control on P680-04 d.
RECIRC Loop B Flow Control on P680-04 l
3 8.
There is a general inconsistent use of color coding f or controls on panels P601 and P870. -Both black and light grey are used for valves and light gray is also used for electrical I
functions.
C-4 l1 I
Clinton 1
~
Audit Report Part C C-4. CONTROLS (Continued)
PRIORITY flNDING 1
9.
The Manual and Automatic positions on several Bailey controllers on P680-03 are inconsistently color coded.
Examples:
a.) RECIRC LOOP A FLOW CONTROL b.) RECIRC LOOP A MASTER CONTROL c.) RECIRC LOOP A FLUX CONTROL d.) RECIRC, LOOP B FLOW CONTROL I
10.
Labels on backlit indicator lights in the control room are easily removeable and are interchangeable.
The labels do not have location identifier codes or keys to prevent interchanging the labels or to identify the correct location of each label.
Example:
UNIT 1 DMPR MTR on P801-66 31 11.
Panels P601-21, P801-66 and P801-67 contain key operated switches oriented with key teeth pointing downward.
These violate the general convention of key teeth up orientation of key switches in the control room.
c 1
12.
Gear shaped control switch knobs used in the control room de not have distinctive visible pointers to indicate switch position.
Examples:
a.) 4160V BUS 1 A control on P870-53 b.) 4160V BUS 18 control on P870-53 c.) 480V BUS control on P870-53 l
.C-5
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Clinton 1 "i
Audit Report' Part C C-5. DISPLAYS l
PRIORITY FINDING r
3 1.
The CYC COND STOR TNK IB LEVEL meter on P870-57 is unnecessary.
1 2.
There are several meters that display mid-scale indications if the meter f ails or becomes inoperative.
Examples:
- a. ) Battery, ion. Current meters on P877-15 fail to the +200 amp irdicat
- b. ) The 4571 VARS meters on P870-15, P601-14X, and P601-15Y fail to a zero indication at mid-scale.
3l 3.
Some displays are not scaled in numerical segments that are readily usable by the operator without mental conversion.
E2ampics:
I a.) The COND POLISHER INLET FLOW meter on P870-57 is scaled in units of 225 per major division and 45 per minor division.
b.) The CDSR VACUUM recorder on P870-58K has unconventional scale divisions in sequence of 6----11----16----21----26.
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3 4
The HP HTR 6A and 6B LEVEL meters on Panel P870-59 have incorrect full scale values compared to intennediate values shown on the meter scales.
Intermediate values on the scales range from -6.0 to +6.0 while the f ull scale values are -65 and
+65.
31 5.
The scale on the unlabeled pressure / vacuum meter on Panel 601-21 is improperly labeled.
The meter displays pressure above the zero marking and displays vacuum below the zero mark.
The scale label for vacuum is aojacent to the 0 - 15 psi pressure portion of the scale instead of adjacent to the 0 - 30 inches Hg vacuum portion of the scale.
1 6.
The small meters on the Bailey controllers on P870-54M are not labeled to identify what parameter is being indicated or the units of the parameter being displayed.
l C-6 l,l 1
Clinton 1 Audit Report Part C f
C-5. DISPLAYS (Continued)
PRIORITY TINDING I
3 7.
The labels identifying units of the scales on some displays are incorrect.
Examples:
a.) The blue pen CORE PLATE DP scale on the JET PUMP FLOW / CORE PLATE DP recorder on P678 should not be a
% scale.
- b. ) The uni,ts.0f the vacuum portion of the scale on the unlabeled pressure / vacuum meter on P601.-21 are erroneously labeled InHgA instead of InHg Vacuum.
1 8.
The scales of multi-pen strip chart recorders are not labeled to clearly identify the variable and units associated with each scale.
Examples:
a.) The scale labels for the ECC SPEED & CONT VLV POSITION l
recorder on P870-59L do not clearly identify the variable associated with each scale.
b.) The RX LEVEL & PRESS RECORDER A on P601-20 does not have labels that identify the variables displayed on either display channel and does not identify the unitse associated with the -160 to +60 scale.
c.) The recorder labels for two pen SUPPRESSION P0OL LEVEL recorders on P601-18 and P601-20 do not identify the second variable displayed on these recorders and there are no labels identif each display channel.ying the variable associated with i
d.) The blue pen channel on the REACTOR WATER LEVEL recorder on P678 is not identified.
e.) Scales are not identified on the PMS TREND recorders 1 &
2 on P680-10E.
f.) Scales are not identified on the NEUTRON MONITORING SYSTEM strip chart recorders on P678.
1 9.
Some strip chart recorders do not have chart paper installed.
t l
1 10.
The scales on some strip chart recorders do not match the scales on the recorder chart paper.
Example:
The ECC SPEED & CONT VLV POSITION recorder on P870-59L has two scales on the recorder and the chart paper installed on the recorder has three scales.
.C-7
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Clinton 1 Audit Report
,r Part C C-5. DISPLAYS (Continued)
PRIORITY ?!NDING 1
11.
The PMS TREND recorders 1 & 2 on P680-10E and the NEUTRON MONITORING SYSTEM strip chart recorders on P678 have multiple scales which are not aligned with each other or with the chart paper.
1
- 12. The label of sca,le units on the CDSR VACUUM recorder on P870-58K is no't visible when the recorder door, is closed.
3
- 13. Flow meters on P601-21 and -22 have nonlinear scales.
Examples:
a.) LPCS PUMP FLOW E21-R600 b.) CRD DRIVE WATER HEAD FLOW c.) CRD HYDRAULICS FLOW d.) CRD COOLING WATER FLOW 3
14 Voltmeters on P870 have nonlinear scales.
Examples:
,e a.) 0-250V RUNNING VOLTAGE on insert 57F b.) 0-250V INCOMING VOLTAGE on insert 57F c.) 480V BUS '!0LTAGE on insert 52G d.) 4'60V BUS VOLTAGE on insert 53H 1
- 15. A vertical series of 8 pairs of red and green inidicator lights on the Remote Shutdown Panel alternate colors left-right down the two columns.
In this arrangement, color and positicr. do not provide any type of redundant information and do not conform to the Close/ Green /Lef t - Open/ Red /Right convention used in the control room.
1 16.
The red zone marking on the GEN HYDROGEN PURITY meter on P870-55M obscures the minor division marks on the meter scale.
3I
- 17. The backlit indicators on P680-06 cannnot readily be distinguished from backlit pushbuttons.
The backlit pushbuttons and indicators are intermixei in the same matrix arrays.
C-8
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I Clinton i e '"'
Audit Report i
Part C l
C-5. DISPLAYS (Continued) t I
PRIORITY YINDING i
i 3I
- 18. Some of the yellow alarm indicator lights on the Remote j
Shutdown Panel do not conform to color code convention.
Examples:
a.) RCIC TURBINE TRIP indicator light
(
b.) RCIC TURBINE OIL TEMP HIGH indicator. light c.) RCIC TURBINE BEARING OIL LOW PRESS indicator light j
(
l 19.
The REACTOR FUEL ZONE LEVEL recorder on P601-2'O is not i
I installed and its space on the panel is not labeled.
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.C-9 l
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l Clinton 1 f
Audit Report g-Part C 1
C-6. LABELS AND LOCATION AIDS i
4 t
i PRIORITY FINDING p
1 1.
A number of labels are missing on controls l
and displays on P680-01, P680-02A, P680-12, P870-56, and P870-59.
Examples:
I
- a. ) Pushbutton controls b.) Throttle handle l
c.) Bailey meters
- d. ) OUTPUT ' SOURCE control j
e.) MN STM TO AUX STM SYS VLV IB21-F395 1
2.
Inconsistent labeling hierarchy and poor label positioning make l
it difficult to associate labels with components on P678.
j l
1 3.
Some permanent labels for the Transfer' switches on the Remote
[
Shutdown Panel do not have switch numbers on them.
Some switches are labeled with numbers using temporary embossed tape labels.
Those labels with switch numbers appear to have i
numbers which are different from the switch numbers cited in the procedures.
.c i
3
'4 The control for the CB Pump Selector on panel P680-02A obscures j
its label.
3I 5.
Labels on the status legend lights on P877-15 do not correspond to the labels on the associated circuit breaker controls.
i I
6.
Abbreviations on labels, location aids, and CRT displays are used inconsistently throughout the control room.
a.) Abbreviations that are not'on the standard abbreviation list are used.
b.) Different abbreviations are used f or the same word.
j 31 7.
There is inconsistent use of abbreviations in meter labels on P801-66 and -67.
In some cases a word is spelled out and in other cases it is abbreviated.
I l
Examples:
{
a.lP801-66SGTSTRAINA i
b., P801-67 SGTS TRN A c.) CONT RM MV TRN B f
d.) SGTS TRAIN B j
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C-10 4
Clinton 1 Audit Report 4
Part C C-6. LABELS AND LOCATION AIDS (Continued)
PRIORITY FINDING 3I 8.
The MSR 1 A DRN VLV RSDV-1 control on P870-56 is not labeled as to direction of operation.
I 9.
The mimic for the Reactor Water Cleanup System on P680-01 has missing mimic lines and termination points..
I
- 10. Some color coding used on mimics does not conform to color code conventions.
The colors used in mimics are not used consistently.
Examples:
a.) On the Water System mimic on P870-56A the SSE Feedwate-is blue (purified water) when it should be green l
(service water / cooling water).
b.) The RCIC mimic on P601 uses a yellow line from the pumps at the botton to the RCIC pump.
The line should be blue according t0 the color coding scheme.
c.) Purified water flow to the CYC COND XFER PUMPS'is shown in green on the water system mimic on P870-57J.
It should be blue.
d.) The Electrical System mimic on P870-SlF shows the 4160V buses in white.
According to the color code, white is used for 345<V and green is used for 4160V.
e.) The mimic on P870-57J contains inconsistent color coding and is incomplete.
I 11.
The Vent System mimic on P800-64 contains a possible error in color coding. Purple should be used for the Drywell vent.
1 12.
Son.e of the arrows are backwards from the actual direction of flow and some line segments and arrows are missing in the RX HD mimic on P601-18 i
l 13.
Insufficient flow direction indicator arrows make it difficult to fcilow the flow paths of the mimic on P800-64R.
I 14 Mimics on several CRT displays lack origin or termination points 1
15.
No grahic representation of a termination point for flow into the suppression pool is provided in the mimic on P601-17.
C.Il
E i
Clinton 1 Audit Report I
Part C C-6. LABELS AND LOCATION AIDS (Continued) 4 i
l PRIORITY TINDING 1
16.
There is temporary mimic on the Remote Shutdown Panel.
1 l
3I 17.
Backpanel 803 has a Switchyard Buses mimic which shows Unit 2 I
i buses.
However, Unit 2 does not yet exist..
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i C-12 ii
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4 Clinton 1 Audit Report i
Part C li C-7. PROCESS COMPUTERS a-1 PRIORITY NINDING 1
1.
The CRT controls on P680 are not labeled.
l 1
2.
Diaracter labels have worn off of some keys on the PMS j
keyboards on P680-10E.
1
]
3 3.
No delay messa'ge is presented to the operator,on the CRT j
display when the response time for operator queries on the PMS j
CRT exceeds 3 seconds.
l I
1 4.
A complete set of computer system operating procedures was not available in the control room and could not be evaluated.
3I 5.
The CRT-1 display for the RWCS SYS on P680 had poor contrast between the characters and background, l
3 6.
On the CRT 8F display of LP TURB B STM INLET TEMP a 60 minute time history is displayed.
The display label does notrindicate clearly that it is a time history display, i
3 7.
Several CRT displays use vertically oriented labels where use i
of horizontal orientation appears possible and would improve readability'.
Examples:
j a.) VESSEL LEVEL CONTROL l
b.) REACTOR WATER CLEANUP SYSTEM i
3 8.
Some CRT displays lack sufficient demarcation of data subgroups.
Examples:
- a. ) TURBINE GEN BEARING SURVEILLANCE b.) RWCUSY/COND SYS STANDBY DATA c.) TURBINE / GENERATOR STANDBY DATA i
i 3
9.
The CRT display of 4A RX RECIRC SYS FLOW CONTROL / MANEUVERING is I
crowded. More than 25% of the total display area is used.
i 3
10.
There is no printar in the Control Room capable of printing
' trend data or plant status data, f
C_-13
i-.
Clinton 1
'j Audit Report h
Part C 1
1 C-7. PROCESS COMPUTERS (Continued)
]
PRIORITY TINDING i
3 11.
The maximum print rate for the Alarm Printer is 60 lines per minute.
The minimum recommended printer speed is 300 lines per minute.
o
]
2
- 12. The Alarm Printer does not print out all annunicator alarms.
j l
2
- 13. Operators will not have the capability to requ'est printouts by j
alarm groups on the Alarm Printer.
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. - ~ - - -
Clinton 1 l
Audit Report
)
Part C C-8. PANEL LAYOUT PRIORITY flNDING I
i 3
1.
The panel layout of functionally related meters and controls on P870-56 is poorly grouped making association between controls and displays difficult.
4 3
2.
The most frequently used STEAM SEAL HDR PRE $5URE -and SSE SHELL i
LEVEL meters on P870-56 are buried within a string of meters i
instead of bei'ng placed in distinctive positio.ns that f acilitate operator reference to them.
31 3.
The PWR SOURCE, PLANT SVC WTR, and CST sections of P601-16 are not separated by any type of functional or system demarcation.
1 I
4 The annunciators controls on several panels are located close I
to other system controls and surrounded by system mimics.
There is no demarcation or color coding to set the annunciator 1
controls apart from the plant system controls and mimic.s i
located in close proximity.
Example:
)
Annunicator controls on P870-51 1
1 3
5.
There is a lack of demarcation to separate two systems on j
P800-62P whose mimics are run together. Both system mimics have the same color flow paths.
2 6.
The "A" System Valve control is located in an out of place position in the "B" System part of the RHR System mimic on P601-17 and is not included in the "A" System mimic.
3 7.
A string of 9 environmental parameter meter.s on P801-66T is too long.
Functionally related displays within the meter string i
are not grouped together.
No demarcation is used to visually break up the long string into readily identifiable sections.
3I 8.
There is a lack of consistent lef t-right order of related adjacent watt and current meters in meter strings on P601-16.
Examples; a.) NORMAL SOURCE watt and current meters b.) RESERVE SOURCE watt and current meters f
C.15 f
Clinton 1 ll~
Aud M Report Part C C-8. PANEL LAYOUT (Continued)
PRIORITY FINDING I
3 9.
Either the mimic labels for the 480V XFMRs J and R on P870-53 are reversed or their associated displays are reversed.
3 10.
The display layout of 480 V BUS V0LTAGE meters in the second row of meters on the vertical panel on P870-52 is inconsistent with the layou,t of similar meters in the third row of meters on the panel.
2
- 11. The control / display relationship layout of the DISCHARGE TEMP displays on P801-67 is reversed with respect to the control / display relationship on P801-66.
Layout on both these panels should be the same.
3I 12.
The AUX & EXTRACTION ' STEAM panel on P870-56A, has a general lack of demarcation.
l 3
- 13. On P800 inserts 63 and 64 there are meter strings containing j
more than five meters.
3 14 There is inconsistent control layout of. controls on P680-04.
1 15.
Two arrays of backlit indicators on P801-66T and 67U that have the identical functions do not have corresponding indicators in the same locations in both arrays.
1 4
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i C-16 l
. _ ~
Clinton 1 Audit Report Part C C-9. CONTROL / DISPLAY INTEGRATION PRIORITY " FINDING 2
1.
The annunicator tile LOSS OF INSTR' AIR ADS RELIEF VLVS is i
located on P870-56 and its associated controls are located across the control room in the Main Steam Section on P601-19.
3 2.
The MS TO SJAE l A INLT VLV, MS TO SJAE IB INLT VLV, SJAE 1A SUCT VLV, and SJAE 18 SUCT VLV controls located on P870-56 are separated from, the associated CDSR VACUUM chart recorder display on P870-58.
2 3.
The meters in the 80P section at the right end of-the Remote Shutdown Panel cannot be read from the locations of associated NSS Division 1 controls in the middle and left sections of the panel.
,c 9
I C-!7 1
Clinton 1 Audit Report Part C C-10. [ EAT.URES THAT COULD NOT BE EVALUATED 1.
Control Room furnishings and equipment were not installed.
Adequacy of furnishings, obstacles to operator movenent, and presence of L
unnecessary furnishings and equipment could not be evaluated.
2.
Communications facilities in the Control Room and at the Remote Shutdown Panel could not be evaluated.
3.
Control Room heatin'g,' ventilation, and air conditio.ning could not be evaluated.
4.
Control Room and Remote Shutdown Panel normal and emergency lighting could not be evaluated.
l j
5.
Control Room auditory environment during normal operating conditions could not be evaluated.
6.
Document organization and ' storage provisions in the Control Room and at the Remote Shutdown Panel could not be evaluated.
7.
Accessibility and use of procedures and other reference documents in the Control Room and at the Remote Shutdown Panel could notche evaluated.
8.
Provisions for storage and maintenance of emergency equipment in the Control Room could not be evaluated.
9.
Compatibility of emergency gear with operators' needs to perform operations while wearing protective equipment could not be evaluated.
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C-18
,