ML20040F895
| ML20040F895 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/22/1982 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | Delgeorge L COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8202100440 | |
| Download: ML20040F895 (41) | |
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PDR JYoungblood LPDR SChesnut NSIC DEisenhut TIC Docket flos.: STN 50-454 SHanauer ACRS (16) and STN 50-455 RMattson JKramer RVollmer Mr. Louis 0. De1 George RHartfield, MPA Q N p
Director of Nuclear Licensing OELD s.
N Commonwealth Edison Company OIE D \\
Post Office Box 767 MRushbrook
.q E C S V E D
,j Chicago, Illinois 60690
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Dear Mr. DelGeorge:
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Subject:
Byron Station Unit 1 Control Room Design Review 6
A u
Enclosed is the Control Room Design Review / Audit Report by the Human Factors Engineering Branch (HFEB) concerning their preliminary review and evaluation of the Byron Station Unit I control room (see Enclosure 1). Since construction of the control room is not complete, this report is based on: (a)your preliminary design assessment (PDA) of the Byron Station Unit 1 control room including your proposal to correct discrepancies, and (b) the HFEB's abbre-viated Control Room Design Review / Audit (CRDR/A) conducted onsite, November 17 through 19, 1981.
Many systems and items were not available for review at the time of the November site visit and must be evaluated prior to issuance of an operating license. These are listed in Part A of this report.
In addition, your proposals on many items identified in the PDA are not acceptable to the staff.
These are listed in Part C of the CRDR/A report along with additional discrep-ancies found by the review team during the site visit. Also, you proposed resolutions to a number of deficiencies which were acceptable to the HFEB.
These are listed in Enclosure 2.
We require that you perform an evaluation of all items not reviewed in the PDA submitted November 17,1981 (Part B) and of all items identified as unacceptable (Part C). Submit your findings, proposed corrective actions, and schedule for implementing the actions. We must receive this information for our review and approval at least 120 days prior to issuance of an operating license.
8202100440 820122 DR ADOCK 05000 ominal Sic,ned b78
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eThe reporting and/or recordkeeping requirements contained in this letter B. J. Youngblood, Chief
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Mr. Louis 0. De1 George Director of Nuclear Licensing Commonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690 cc: Mr. William Kortier
' Mr. James G. Keppler Atomic Power Distribution U. S. NRC, Region III Westinghouse Electric Corporation 799 Roosevelt Road P. O. Box 355 Glen Ellyn, Illinois 60137 Pittsburgh, Pennsylvania 15230 Paul M. Murphy, Esq.
Isham, Lincoln & Beale One First National Plaza 42nd Floor Chicago, Illinois 60603 Mrs. Phillip B. Johnson 1907 Stratford Lane Rockford, Illinois 61107 Ms. Bridget Little Rorem Appleseed Coordinator 117 North Linden Street Essex, Illinois 60935 Dr. Bruce von Zellen Department of Biological Sciences Northern Illinois University DeKalb, Illinois 61107 Mr. Edward R. Crass Nuclear Safeguards and Licensing Division Sargent & Lundy Engineers 55 East Monroe Street Chicago, Illinois 60603 Myron Cherry, Esq.
Cherry, Flynn and Kanter 1 IBM Plaza, Suite 4501 Chicago, Illinois 60611 Mr. William Fourney U. S. Nuclear Regulatory Comission Byron / Resident Inspectors Office 4448 German Church Road Byron, Illinois 61010 Ms. Diane Chavez 602 Oak Street, Apt. #4 Rockford, Illinois 61108
ENCLOSURE 1 HUMAN FACTORS ENGINEERING CONTROL ROOM DESIGN REVIEW / AUDIT REPORT BYRON GENERATING STATION COMMONWEALTH EDISON COMPANY Introduction A human factors engineering design review / audit of the ByTxan Unit 1 control room was performed at the site on November 17 through November 19, 1981. This review was accomplished using the Unit 2 control room appropriately mocked-up to reflect design changes already conmitted to be incorporated in Unit 1.
The report was prepared on the basis of the HFEB's audit of thie applicant's Preliminary Design Assessment report and the human factors engineering design review performed at the site. This design review was carried out by a team from the Human Factors Engineering Branen, Division of Human Factors Safety.
The review team was assisted by consultants from BioTechnoEogy, Inc. (Falls Church, Virginia), and from Lawrence Livennore National Ldmoratory (University of California) Livermore, California.
Observed human f actors design discrepancies were given a priority rating of 1, 2, or 3 (high, moderate or low), based on the increased pesential for operator error and the possible consequences of that error. Priorfty. rating 1 and 2 discrepancies should be corrected prior to issuance of an mperating license.
Priority rating 3 discrepancies should be evaluated and prmposed actions reported as part of the long-term desico review in accordance with the guidance provided in NyREG-0700. Note.nat some priority 3 ratings include a superscript 1 (i.e., 3 ).
Since priority 3 discrepancies involve simple corrective actions relative to the potential for improving operator performance, tney should also be corrected prior to issuancea of an operating license.
A list of those items that could not be evaluated is presemted in Section A of this report. The condition of construction or installatiom of these items at the time of the site visit was not sufficiently finalized to permit review.
Section B of this report contains a list of items which the review team-determined not to be valid discrepancies for the reasons stated, or were satisfactorily corrected prior to the audit.
The findings in Section C are numbered to conform to the guidelines of NUREG-0700 and summarize the team's observations of the comtrol room design and layout and of the control room operators' interf ace with the control room environment. The numbers in parentheses correspond to sections and items of the PDA, submitted November 17,1981, (4.X.X), or a preliminary draft of the PDA,(2.X.X.X).
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It is expected that the Unit 1 and Unit 2 control rooms will be exact duplicates, and that the licensee's commitments to correct discrepancies included in this report will apply to both.
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HUMAN FACTORS ENGINEERING CONTROL ROOM DESIGN REVIEW / AUDIT REPORT BYRON GENERATING STATION j
COMMONWEALTH EDISON COMPANY j
A.
SYSTEMS AND ITEMS NOT AVAILABLE FOR HFEB REVIEW l
This section lists those systems and items which were not available for review during the HFEB site visit of November 17 through 19, 1981. These systems and items must be reviewed and evaluated by the applicant, and any deficiencies that are identified must be corrected prior to issuance of an operating license.
1.0 CONTROL ROOM WORKSPACE A.
Communications from desks / consoles to other parts of the control room B.
Communications between the control room and the shift supervisor's office C. ' Center desk design, function, and personnel interface D.
Document organization and storage E.
Organization and storage of spare parts, operating expendables, and tools F.
Control room access control G.
Control room furnishings H.
Emergency equipment and its storage I.
Environment (illumination, temperature, humidity, ventilatiop; and audition) 2.0 COMMUNICATIONS All items except those listed in Section 2.0 of the HFEB Review / Audit Team Findings (part C of this report).
C 3.0 ANNUNCIATOR WARNING SYSTEM Annunciator auditory alarms 4.0-CONTROLS A.
All controls covered by or represented by mock-ups.
B.
The HFEB review did not include measurements of resistance and/or displacement or torque of round pushbuttons, legend pushbuttons, key operated controls, continuous adjustment rotary controls, rotary selector controls, thumbwheels, and toggle switches.
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5.0 DISPLAYS A.
All displays covered by or represented by mock-ups.
B.
Legend lights that were not engraved or activated; e.g.,
1.
- 2. _ Auxiliary feedwater 3.
By-pass permissive 4.
Trip status 5.
Loop stop-valve permissive 4
i 6.0 LABELS AND LOCATION AIDS Tag'ging procedures.
7.0 PROCESS COMPUTERS All items except data entry-keyboards, computer function controls, data point indices, CRT display controls, operator-display relationships, i
printer characteristics, and alarm messages.
8.0 PANEL LAYOUT and 9.0 CONTROL-DISPLAi INTEGRATI0M A.
Panels IPM0lJ and IPM02J must be re-evaluated when they have been completed.
B.
The Remote Shutdown panel must be re-evaluated after the planned mimic is installed.
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HUMAN FACTORS ENGINEERING CONTROL ROOM DESIGN REVIEW / AUDIT REPORT BYRON GENERATING STATION COMM0FiEALTH EDISON COMPANY B.
ITEMS THAT ARE NOT VALID DISCPF TNCIES. OR WERE SATISFACTORILY LORRtGTED PRIOR M J THE AUDIT 3.0 ANNUNCIATOR WARNING SYSTEMS
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PDA FINDING (4.3.2)
There is only one location for the display of first-out alarms.
All first-out alarms should be available immediately above the associated panel.
Reason The first-out alarms are located above the associated panel.
(4.3.3)
First, second, and third priority alarms are noE displayed in the control rocm.
Reason First, second, and third level alarms are provided.
(4.3.5)
Operator aids for annunciator lamp replacement are not available.
Reason A lamp tool is not needed for annunciator lights.
C (2.3.3.2-6)
The first-out annunciators indication for reactor trip is reset wnen other annunciators on this panel are reset.
Reason A separate set of first-out annunciator controls has already been installed.
5.0 VISUAL DISPLAYS (4.5.2)
All displays should indicate values in a fonn inmediately usable by the operator without requiring mental conversion. The RCP Seal water flow, RHR-HX water flow, and RC Loop flow require the operator to,6entally conve.rt, the information pr,esented.
(4.5.2) 2.gu.
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Reason Discussion ~s with* 6perators revealed that mental conversions were not a requirement in monitoring the disp, lays.
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HUMAN FACTORS ENGINEERING CONTROL ROOM DESIGN REVIEW / AUDIT REPORT BYRON GENERATING STATION COMMONWEALTH EDISON COMPANY C.
HFEB REVIEW / AUDIT TEAM FINDINGS 1.0 CONTROL ROOM WORKSPACE PRIORITY RATING FINDING 3
1.
The design of the control room does not facilitate unobstructed movement and communication. For example, an operator seated at the Center Desk must traverse approximately 30 feet around the desk to reach a position that is only 10 feet away on.a straight line. The design of the Center Desk may impair performamoe of the reactor operator / senior reactor operator stationed at the desk.
(4.1.1) (2.1.1-1) 1 2.
Some of the controls on the stand-up consble are located out of the reach of the 5th% height operator. The highest control is located 65" from the floor (recommended maximum = 60").
(4.1.2) 3 3.
The 30" depth of the benchboard (recommended maximum'=
25.2") will force the 5th% height operator to lean over the panel. This depth increases the probability that the controls on the benchboard edge will be accidentally activated.
(4.1.2) 1 4
Some controls on the common vertical panels are mounted above and below the recommended 34"-70" meight range.
The c
lowest controls are 12" from the floor. The highest controls are 87" from the floor.
(4.1.3) 1 5.
Some displays on the common vertical panels are mounted above and below the recommended 41"-70" height range.
The lowest display is located 23" from the floor.
The highest display is located 92" from the floor. The top rows of the annunciators are located 90" from the floor (4.1.3).
1 6.
Annunciator response controls on the vertical panels are located 77" from the floor, making operation of these frequently used controls difficult.
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1.0 CONTROL ROOM WORKSPACE (Continued)
PRIORITY RATING FINDING 1
7.
The equipment located at OPM05J,. Center Desk, and the desk's general location are inappropriate for the desk's primary function as the only senior reactor operator-station. The desk has fire alarm annunciator panels on most sections and it is surrounded by shared and auxiliary, panels.
3 8.
The design of OPM05J, Center Desk, prevents the seated operator from having full view of all of the controls and indicators on OPM02J.
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The copper pipes which will supply emergency breathing air currently stick out of the control roma floor, and present a tripping hazard.
3 10.
The leg openings in the wing sections of OPM05J, Center Desk, do not provide the recommended 30" lateral leg space for a seated operator. The lateral leg space provided is 23".
I 11.
The annunciators on the vertical panels are oriented at less than the recommended minimum 450 angle to the line of site from the position of the associated response controls.
I 12.
Controls and displays on the Remote Shutdown panel are mounted outside the recommenced height ranges.
Controls are located 29"-68" from the floor (recc= mended range =
34"-70").
Displays are 'ocated 41"-88" from the floor (recommended range = 41"-70").
2 13.
No plans have been made to provide protective clothing for control room operators, except for full hood / face masks c
with air lines.
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2.0 C0KMUNICATIONS PRIORITY RATING FINDING 3
1.
The sound-powered phone headsets are uncomfortable to wear for long periods of time.
(4.2.1) (2.1.2-1) 2 2.
Neither the PA system nor the conventional phone system handsets have cords long enough for use at all parts of the control board.
(4.2.2) 31 3.
The Press-to-talk and Channel Select switches on the pa system are located too low to be operated effectively. ging (4.2.3) (2.3.3.2-3) e O
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3.0 ANNUNCIATOR WARNING SYSTEMS PRIORITY RATING-FINDING
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First-out indications occur on separate but undedicated panels for:
o Reactor Trip (24 tiles) o Turbine Trip (10 tiles) o Generator Trip (20 tiles) o Feedwater Pumps Trip (2 tiles)
The first-out tiles are intermixed with other tiles.
(4.3.1)(2.1.3-2) 1 2.
Tiles on the following annunciator paneils are not readable from acknowledge buttons: Annunciator Panels UL-AN026, 003, 007, 008 012, 014, and 015.
(4.3.4) (2.1.1-2)
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3.
No procedure exists to describe annunciator tiles which
. must be "on" for extended periods of tisse. (4.3.4) 2 4.
Some annunciator alarm tiles are not located above related controls and displays and do not reflect proper functional grouping or axis labeling.
(4.3.4)(2.1.3-1)
Tile Comment 2E02 Should be duplicated on IPM01J 2007 Should be on IPM0lJ 2E07 Should be on IPM0lJ 3A05 Should be on IPM0ld 6A05" 6806l 6C06]
6A07]
Boron injection tank is-6607' removed - tiles are 6C07 unnecess ary 6D07]
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Controls are far from 15C10]
15D10:
Consider duplicating 15E07 these tiles on IPM06J 15E08]
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. hot on c'ommon panel OPM0lJ
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18816 19A06 Not located in the first out group C-4
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PRIORITY RATING FINDING 1
5.
A separate alarm horn is needed for each section of the control board. (4:3.6)(2.3.3.1-2) 1 6.
A manually initiated annunciator audio block is available for the Feedwater, Condensate and Turbine Control panels.
Two red alternating flashing lignts indicate when. the block is in use. The annunciator silence buttons silence only a single audible alarm, whereas the guidelines state that it should be possible to silence an auditory alert signal from any set of annunciator response controis in the primary operating area.
(2.3.3.2-4) 3 7.
The annunciator flash rate is about 2 flashes /second instead of the recommended 3 to 5 flashes /second.
3 8.
Annunciator panels on IPM0ld,1PM02J, and IPM03J have more than 50 tiles, the recommended maximum number of tiles per panel.
31 9.
Some annunciator tiles are not permanently engraved. Some annunciator tiles are' labeled with temporary labels.
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4.0 CONTROLS (Continued)
PRIORITY RATING FINDING 3
9.
The BORIC ACID / PRIMARY WATER batch make-up thumbwheels on IPM05J are much smaller than recomended, which could cause operating difficulty.
(4.4.14) 3 10.
The IN-CORE THERMOCOUPLE toggle switches do not snap into position, and are not labeled to indicate either the direction of movement or of activation.- (4.4.15)
I 3
11.
The Tave and DELTA T defeat switches do not have to be pulled to actuate as do the corresponding switches at the Zion Station.
(4.4.18)(2.3.3.2-2)
I 3
12.
On IPM06J the same type of control handles are used for valves with different functions. An operator cannot differentiate among throttleable, open/close, and throttle open-seal close valves.
(4.4.19)(2.3.3.1-9) 1 13.
The REACTOR TRIP and REACTOR RESET functions are on the same switch.
(2.3.3.2-1) 2 14.
The J-handle control switches on the Remote Shutdown panel can be inadvertently activated.
2 15.
The PLANT EVACUATION ALARM and plant-wide FIRE ALARM pushbuttons on the Remote Shutdown panel can be accidentally activatec.
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The Remote Shutdown panel J-handle switches do not have the pointer arrows filled in with contrasting pigment for easy visibility.
2 17.
Several controls on the RAMTEC CRT are not useful to the operator and might interfere with the display if activated.
2 18.
The ALARM PRINTER CONSOLE control box has many keys and controls which the operator is not permitted to use. When i
I locked "off" the printer keyboard is not available to the control room cperator.
3 19.
On IPM08J the thermoccuple toggle switch bank is subject to breakage because the switch handles extend into the ' -affic area.
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The switch guards for the C-W MAKEUP EMERGENCY TRIP controls on OPM0lJ obscure 4he pushbuttons and their color t
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m 4.0 CONTROLS (Continued)
PRIORITY RATING FINDING 1
21.
On OPM05J, the PLANT EVACUATION ALARM pushbutton guard has an ear for a padlock.
If the ear was bent over, the guard could not be raised to operate the pushbutton.
3I 22, On the Reactor end of IPM05J, Reactor and Chemical and Volume Control panel, and on IPM06J, Engineered Safeguards panel, one switch in each string maintains trip contact position while all the rest are spring return.
3 23.
On 1PM12J, Miscellaneous Instrumentati6n panel, three modules (POWER SUPPLY, ALARM AND TRIP RELAY, and VIBR PHASE ANGLE) have slotted non-locking selector controls which are flush with the panel. The slot serves both to turn the control and to indicate its selected position.
It is not clear which end of the slot indicates the position selected.
3I 24.
On 1PM02J, Turbine panel, the legends on the REHEAT TURBINE controller pushbuttons do not relate to the system controlled:
o GROUP 1 out of service corresponds to" Governor End" o
GROUP 2 out of service corresponds to " Generator Eno".
1 25.
On IPM11J, Containment Isolation back panel, two rotary '
selector switches lack control position indications.
1 26.
On 1PM08J, In-Core Instrumentation panel, the DETECTOR E 3
knob pointer mark does not extend to the position incication mark because of tne knob's black skirt.
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27.
On 1PM05J, the LAMP TEST control knob pointer mark does not extend to the position indication mark on the panel because of the high raised knob, which also causes parallax.
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28.
On 1PM08J, In-Core Instrumentation panel, it is difficult to read the switch position on the 261 PICO AMP SOURCE controls because the knob obscures the switch position window.
3I 2 9 '.
On OPM0lJ, two of the CW MAKE-UP PUMP EMERGENCY TRIP switches have red back plates while the third switch does not.
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5.0 VISUAL DISPLAYS PRIORITY RATING FINDING 1
1.
The 100% readings on some of the M/A Station Switches -
indicates valves are 100% open; on others it indicates that the valves are 100% closed. This could cause incorrect valve operation.
(4.4.5) (2.2.1-1) (2.3.3.1-8) l 3
2.
The ROD SPEED linear scale indicator increases down rather than up.
This is inconsistent with other indicators and could lead to confusion.
(4.4.6)
-1 3.
All legend pushbuttons and indicator light lenses are removable from the front of the panel for bulb replacement, but they are also interchangeable within a particular panel or display.
It is therefore possible that inadvertent changes can be made in the locations of the pushbutton/ indicator light lenses when more than one bulb is replaced.
(4.4.8)(2.2.3-1) 3I 4.
A 0-800 psi RCS pressure gauge by the LETDOWM/ CHARGING system is needed for low pressure operations an RHR.
(4.4.16)(2.2.3-5) 3 5.
Inconsistent type styles are evident on the displays throughout the control room.
(4.5.3) (4.5.6) 3 6.
The meaning assigned to particular colors should be consistent across all applications within the control room, whether applied to panel surfaces, projected in red, green and amber coloreo lights, or on CRT's.
Colors shoula be reserved for specific uses. Green board, RAD monitors, permissives, and system status are not in compliance.
(4.5.4) 3 7.
Vertical meter pointer tips do not extend to within 1/16" c
of the smallest graduation marks on the scale.
(4.5.5) 3I 8.
The LUBE OIL RESERVOIR linear scale display has no label indicating what is being read (e.g., inc.hes, lbs., percent, etc.). The scale ranga is 0 to 120.
(4.5.6) (2.2.3-4) 2 9.
The recorders are not all designed to permit monitoring of cata without oper.-door operation.
(4.5.7) 3 10.
The PRIMARY WATER CONTROL PRE-COUNT digital groupings are longer than four digits, but they are not separated by comas, decimal points, or additional spaces, as y
recognended. f4.5.8).,
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3 11.
The bus meters have too large.a scale for accuracy of required reading.
(4. '5.9) ( 2.2.3-3 )
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T 5.0 VISUAL DISPLAYS (Continued)
PRIORITY RATING FINDING 2
12.
The CENTRIFUGAL CHARGING PUMP mini-flow valves.are required to be closed when reactor pressure falls below 2000 psig following a safety injection. With no min.i-flow available, there is a possibility of overheating the pumps if system pressure increases.
During this activity the operator is required to remember to monitor the REACTOR COOLANT SYSTEM pressure to assure it does not exceed a set point.
(4.5.10)(2.3.2-2) 31 13.
Zion Station operating experience showed that a semi-gloss-flourescent orange pointer on the vertical meters appeared to improve pointer recognition when presented on a white or green band background.
(4.5.11) (2.3.3.1-1) 2 14.
Zion Station operating experience indicated that the use of a green normal operating band would alert operators to abnormal conditions when the pointer tas not in the appropriate range.
(4.5.12) (2.3.3.1-4, 2.3.3.1-6) 2 15.
Adequate tools are not present in the control room for indicator bulb replacement.
2 16.
On the Remote Shutdown panel, normal operating limits are not marked on the meters.
3 17.
The Westinghouse J-handle switches have incorporated-indicator flags that originally indicated the status of the control.
These flags have been mace obsolete by the installation of a new system of NORMAL / ABNORMAL indicator lights. The colored flags are still visible, and may present confusing information to the operator.
2 18.
Illuminated legend pushbuttons are not readily c
distinguishable from illuminated legend indicators.
3 19.
The COMPONENT COOLING ammeter on OPM02J and several meters on the Remote Shutdown panel lack a number at the top-most end of the. display scale.
In addition, the ammeter scale has an unconventional end-point.
I 20.
All top-level curved'f ace meters on the Remote Shutdown panel are very high, and have vertical labeling which is obscured by the meter curvature.
I 3
21.
On IPM04J, Steam Generator and Feedwater panel, the legend indic.ator type is too,smal.1 to read easi.ly..
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5.0. VISUAL DISPLAYS (Continued)
PRIORITY RATING FINDING 3l 22.
Several meters have inconsistent unit labels.
o On 1PM06J some labels read only "%" with "xxx" on an external Iabel, others raad "%xxx" on the meter face.
o.On IPM02J, the GENERATOR H2 TEMP reads CC.
All others read 0F.
o On IPM04J, different unit designations are used for identical units on the FEEDWATER FLOld meters:
FW FLOW - PPH x 106 FW P. UMP DISFLOW - KLB/HR x 103 1
23.
The CONTAINMENT PRESSURE recorder scale on IPM06J shows no units.
31 24.
Many abbreviations found on control room meters and annunciators are not in the standard abbreviation list.
Many others are not consistent with the list.
1 25.
The A,B,C,0 STEAM GENERATOR LEVEL meter faces on 1PM04J have incorrect % signs and Roman numeral labeling within groups of 4 meters.
i.e.,
I,II,III,II should be I,II,III,IV.
31 26.
The CNDS STORAGE TK LEVEL indicator meter on IPM0lJ nas a temporary meter scale.
3I 27.
On the Remote Shutdown panel the SRI COUNT RATE meter has a log scali with very small intermediate graduation numerals.
2 28.
The green RODS IN and red PODS OUT indicator lights on IPM05J are inconsistent with the plant color coding convention.
31 29.
The Gaitronics paging system has a red MERGE pushbutton and a green ISOLATE pushbutton, which is an. inappropriate use of these colors.
3 30.
On the Remote Shutdown panel the pointers on the Hagan Manual / Auto stations cover the numerals of the display.
3 31.
On IPM05J, there is severe parallax when reading the green pointer of the two pen recorders because it is behind the recorder scale.
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5.0 VISUAL DISPLAYS (Continued)
PRIORITY RATING FINDING 2
32.
The indicator light color coding convention used for the group of EXHAUST FANS controls on IPM02J and the group of B0OSTER PUMPS controls on IPM03J is green = off, blue =
run, and amber = tripped. The normal condition for these lights is three blue (run) and one green (off, but in standby). This violates the control room color coding convention of green = normal.
2 33.
On OPM02J, DIFFERENTIAL PRESSURE meters are not consistent in the use of (-) and (+) values. The (-) and (+) symbols should be on the meter face.
2 34.
There are incorrect bulbs of different brightness in some indicator lights. GE1819 should be for annunciators, GE1835 should be for indicators. When a GE1819 bulb is installed in an indicator, the indicator legend is too dim.
31 35.
There is an unknown and unlabeled indicator light on IPM0lJ.
2 36.
Multiple red / green indicator lights have no integral labeling to describe their function on 1PM04J (DRAIN VALVES) and IPM06J (SVAG VALVES).
2 37.
On IPM04J there is inconsistent use of color for indicator lights, and some lights are not labeled.
q l
38.
On IPM04J, there are many cases of incorrect indicator legend caps, e.g., FW PUMP DISCHARGE valve open/close indicators are mounted opposite from the proper indication, and the red lights for the FW PUMP 2C OIL PUMPS should be blue.
I 3
39.
There is an inconsistent use of 2 different styles of red c
and green switch indicator lights on IPMO6J.
1 40.
There is inconsistent color coding of indicator lights for the REACTOR CONTAINMENT FAN switches on IPM06J. They are green-amber-green instead of green-amber-blue.
This may be a problem on other panels.
8 6
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6.0 LABELS AND LOCATION AIDS l
PRIORITY RATING FINDING
^
y 1
1.
The labeling on some of the 3-way valves is unclear.
(4.4.17) (2.2.2-3) (2.3.3.1-7) 1 2.
Many controls, displays and other equipment items are unlabeled.
(4.6.1)
I 3
3.
Hierarchical and functional group labeling is not presently available on the control boards or on the Remote Shutdown panel to assist the operator and to simplify the component labeling.
(4.6.2)(2.3.3.1-5) i 2
4.
The Hagan controllers have labeling that is inconsistent with the other labeling in the control room. The Hagan Manual / Auto stations have redundant labeling.
(4.6.3) 31 5.
On IPM02J, display labeis are generally placed below displays rather than above, as is recoteended.
(4.6.3) 1 6.
The maintenance tags obscure adjacent labels, displays, and indicator lights. (4.6.4) (2.1.4-1) 3I 7.
Some of the labels and location aids in the control room can be. easily removed. Demarcation lines also are not permanently attached.
(4.6.5) (4.6.7)
I 3
8.
Some control board labels use inconsistent abbreviations.
(4.6.6) 31 9.
Some control board labels use inconsistent color coding schemes.
(2.1.4-2) 31 10.
The Zion operators specifically mentioned the need for mimics on the Chemical /.tnd Volume Control System, Boric c
Acid, and Engineered Safeguards panels.
(2.3.1-A,
- 2. 3. 3.1 -3 )
3I 11.
There is a lack of background shading to. enhance the operator's ability to differentiate among functional grouping of instruments and controls.
(2.3.1-B)
?.
12.
The circular meter displays used throughout the control room have curved descriptive labels on their faces.
3I 13.
There are no panel number identification labels.
I m
3 14.
A labe'l on OPM02J has a._ misspelled word;..VAVLE is used instead of VALTE.- Another. label on OPM02J incorrectly
= =.,.
reads CLAND inst,ead of, GLAND,.
t C-13
6.0 LABELS AND LOCATION AIDS (Continued)
PRIORITY RATING FINDING 3I 15.
Several three position J-handle controls in the control room have only two of the positions used. Mechanical stops have been provided to prevent moving the controls to -the unused position, but the position indicator marks are still engraved and filled with dark pigment.
I 16.
The AUXILI ARY BUILDING FILTER PLENUM 8 control on OPM02J is missing the position labeling.
1 17.
In the PHASE B CONTAINMENT ISOLATION ori 1PM06J, manual i
actuation requires that two controls be activated simultaneously. There is no indication of this requirement on the controls.
I 31 18.
Therr. are several cases of labels being obscured by equipment in the control room, e.g., the label for the GENERATOR H2 COOLING WATER VALVE indicator lights is obscured by the recorder located above them, and some labels at the top of IPM07J are obscured by their associated controls.
3I 19.
The approximately 12x2 bank of CONDENSATE CONTROL control's on the vertical section of 1PM03J are not demarcated.
This makes differentiation among the controls difficult.
I 3
20.
The proposed demarcation lines on IPM04J 00 not clearly associate the two status light arrays on this panel with their functionally related controls and displays.
3I 21.
The labels describing pen assigments on the ROD INSERTION LIMITS recorder and the CW COOLING TOWER TEMPERATURE recorder are placed on the glass f ace of the recorder where they obscure the chart paper.
c 31 22.
Tne recorder that displays the parameters selected by the process ccmputer is not clearly labeled as to its function. The label for this recorder reads only COMPUTER.
2 23.
On OPM05J, Center Desk, engraved labels for TROUBLE, FIRE, and WIRE-TROUBLE are not specific enough to provide the necessary information. The same labels are used on 280 different legend light indicators.
1 24.
Many component labels do not indicate what is being displayed. For example, the labels for the WIDE RANGE RTD w
displ_ays on the Remo.te, Shutdown panel do..not. indicate that hot.and cold lig temperatures are being displayed. Also, w.
the labels for the met.ers.on. LPM 02J, which display the inlet pres'sure'f' rom the moisture separator reheater to the three low pressure turbines', do not clearly identify what is being measured by the meters.
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E.0 LABELS AND LOCATION AIDS (Continued)
PRIORITY
~
RATING FINDING
~
1 25.
The nomenclature on the Remote Shutdown panel transfer control switches is unclear. The two position choices are REMOTE and LOCAL. Although the panel is the " remote" panel, R940TE means that control is located in the control ro om. LOCAL indicates that control is located at the Remote Shutdown panel.
2 26.
Grouped meters with different functions are not adequately differentiated by their component labels. For exanple, all six labels for the meters that display the inlet pressure from the moisture separator reheater to the three low pressure turbines are very similar, making differentiation between them difficult.
I 3
27.
The test positions on the SGFPT 2 C LUBE 0IL RESERVOIR TEST control on IPM04J are OLL for " oil level low" and OLH for
" oil level high." Since these abbreviations are very similar, it is hard to differentiate between the two different meanings.
2 28.
The labeling, lettering, and terms used on the Westinghouse-provided panel inserts are not consistent with the other control room labeling.
1 3
29.
There are cases of adjacent controls of the same kind that have position labels with different size and style type face.
3I 30.
The standard black-on-white labels used in the control room come in several different " shades" of white and off-white.
The engraving styles and depths are also not consistent for all the labels.
O 31 31.
Some of the color comoinations used do not provide adequate contrast. For example, the labeling on the 1530/ST101 SCALER TIMER panel insert on IPM07J is beige-on-beige and
-is very difficult to read. The black-on-orange labels used for train differentiation are also of poor contrast.
I 3
32.
The annunciator response button legends and some of the control position label character heights are too small to be read by a 95th% height operator. The recommended character height (0.004 'x viewing distance) is 0.15".
The measured height was approximately 0.11".
This finding applie,s to labels and legends on the lowest part of the sloping section, of the, benchboard.
-;_z I
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3 33.
There are temporary ca.ution. cotes on IPM06J which should be removed or' Feplaced prior to operation.
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6.0 LABELS AND LOCATION AIDS (Continued)
PRIORITY RATING FINDING I
3 34.
The Remote Shutdown panel lacks any demarcation or other location aids to identify functionally related groups of controls and displays.
31 35.
There is insufficient demarcation between the ACCUMULATOR,.
SAFETY INJECTION, and RESIDUAL HEAT REMOVAL mimics. These mimics are intermingled on 1PM05J and IPM06J.
I 3
36.
On IPM03J, the indicator lights for the HEATER DRAIN TANK VALVE need demarcation and label change's.
3I 37.
Sections of mimic lines are missing between two circuit breaker controls and some indicator lights in the AUXILIARY POWER mimic, 31 38.
The BTRS DEMINERALIZER mimic and the REACTOR COOLANT PUMP SEALS mimic are designed around controls that are in one large array. It is very difficult to see where one mimic ends and where the other begins, 3I 39.
Tne CVCS LETOOWN mimic does not have a label icantifying the flow origination point.
3I 40.
None of the mimics have arrows to indicate the direction of each flow path.
3 41.
On the 69KV mimic on IPM0ld, the symcol for the DISCONNECT-GROUNDING switch does not depict the switch functions as clearly as do the corresponding symbols for the same switch which are used in the mimic on OPM03J.
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F 7.
PROCESS COMPUTERS PRIORITY RATING-FINDING 3
1.
The CRT terminal and the Sequence-of-Events printer have differently arranged keyboards.
I' 3
2.
On ICX05J, Computer Operator console, functions are now available to the control room staff that they do not need.
Also, keys are available on the keyboard that control room operators do not need.
4 2
-3.
Procedures for cases where the process computer fails are not available to the operator.
2 4.
On 1CX05J, data point addresses are not cross-indexed by program name, system / subsystem, and functional group.
I 3
5.
Individual data groups or messages do not have descriptive titles which reflect the unique characteristics of the content of the data groups or messages.
3 6.
There is no hard copy facility available to print out displays which appear on the RAMTEC CRT. -
2 7.
The 1CX05J Terminet 1200 printer prints at only 120
~
characters /second. The reccmmended speed is 300 lines / minute.
31 8.
The Terminet printers do not have a paper take-up device for the printed record.
3 9.
The Sequence-of-Events recorder does not identify the associatbd annunciator tile which has alarmed.
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8.
PANEL LAYOUT PRIORITY l
RATING FINDING 2
1.
On IPM04J, the FEEDWATER PUMP TURBINE CONTROL pushbuttons are not arranged in a natural, stereotypical, or logical sequence increasing the probability of inadvertent /
accidental activation of the wrong control (e.g., valve OPEN button is to left of valve CLOSE button).
(4.4.4) 3 2.
There is inadequate separati-on between groups of displays on IPM0lJ, Power Generation panel.
(4.8.1) 3 3.
Sets of controls and displays on 1PM0lJ Power Generation panel, are not consistently layed out. Layouts of some repeated functions are mirror imaged, e.g., WATER ISOLATION VALVES, mini-flow valves for RHR PUMPS 2A and 2B, and ACTIVATED VALVES.
(4.8.2) 1 4.
To avoid leaving the Reactor panel unattended during startup, operators require another person to change the range and volume of the SOURCE RANGE nuclear instrument.
(2.3.3.2.-5) 3 5.
On IPM06J, Essential Service Water panel,'the meters are aligned PA PB-TlA TlB T2A T2B. Pressures and temperatures are not to be compared. Better grouping would be PA TlA T2A - PB TlB T28-3 6.
On OPM05J, Center Desk, DETECTOR and SUPPRESSION indicators are on separate panels. Better grouping might ce if all indicators for a given zone were in one area.
3 7.
On IPM0lJ, Generator and Auxiliary Power panel, grouped meters have different functions but are not differentiated.
(2.3.3.1-5) c 3
8.
On IPMC6J, the AUXILI ARY FW CONT indicator lights for SG1, SG2, SG3 and SG4 valves are not functionally grouped.
3I 9.
Because of the almost total lack of demarcation, it is not obvious that IPM03J is well layed out and functionally gro uped. Demarcation is specifically needed to separate the Condensate section of IPM03J from the Turoine section of 1PM02J. There is presently no board break or demarcation between the closely spaced equipment.
3I 10.
On IPM05J, demarcation has not been used to separate intenningled groups.of, equ.ipment, e.g., JIIS instrumentation w
and.CVCS contrdisand displays.
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8.
PANEL LAYOUT (Continued)
PRIORITY
~
RATING FINDING
~
~
I 11.
On IPM05J, the REACTOR COOLANT ORAIN TANK PUMP controlc are 3
located about four feet away from other functionally related controls.
31 12.
On IPM05J, the REACTOR COOLANT DRAIN TANK PUMP caritrols appear to be functionally grouped with the RANGE MANUAL BLOCK controls located directly above them. Both groups use the same model switch, but there is no demarcation between them.
3I 13.
The REACTOR COOLANT SEALS mimic and the BTRS mimic are both on 2PM05J, Reactor and Chemical and Volume Control panel.
Several controis which are not in either mimic are associated with one of the mimics. A third mimic intrudes, also, on the BTRS mimic.
It is difficult to tell what is in one mimic, what is in the other mimic, and whart is not in either mimic.
3I 14.
Functionally grouped systems are not adequately distinguishable on IPM0lJ.
I 3
15.
On IPM03J, Condensate panel, associated controls a:nd displays are presently separated by unassociated controls and displays.
3I 16.
On the Remote Shutdown panel, the STEAM GENERATOP. controls and meters are separated by the AUXILARY FEEDWATER controls.
I 17.
The legend light groups on IPM06J, Engineered Safeguards 0
panel, are misoriented by 90.
3 18.
On OPM02J, HVAC panel, the UNIT 1 and UNIT 2 CONTAIN!ENT and VENTILATION controls and displays are laid out identically except for the pressure meters, which are mirror imaged.
2 19.
There is an inconsistent layout on IPM05J, Reactor and Chemical and Volume Control panel. The ROD BANK COUNTER groups have SHUTDOWN on left and CONTROL on right, whereas DIGITAL ROD POSITION indicator shows the reverse-SHUTDOWN on right, and CONTROL on left.
3 20.
The DIGITAL ELECTRO HYDRAULIC TURBINE CONTROL numeric pad (telephone type) is different from the computer mumeric panels,.(adding machine type).
3 21.
On 1Pi406J, the*STENiiENERATOR and AUXILIARY FEEDWATER PUMP
==r controls are mirror im. aged,_but the remainder of the panel is not.
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8.
PANEL LAYOUT (Continued)
PRIORITY RATING FINDING i
3 22.
The CONTAINMENT SPRAY system on IPM06J is mirror imaged for no apparent reason.
1 23.
On the Remote Shutdown panel, the TRAIN A and B displays and controls are mirror imaged over a total distance of 12 to 13 feet.
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9.
CONTROL-DISPLAY INTEGRATION PRIORITY RATING FINDING r.
i 2
1.
The RCP SEAL FLOW control is adjusted while monitoring HEADER PRESSURE indicators, IPM05J. The displays and controls are not located within reasonable proximity.
(4.5.1) (4.9.1).
2 2.
The SEAL INJECTION FLOW indicators are located on. the left at the top of 1PM05J.
The HCV 182 controller is on the.
left front diagonal panel at the bottom of the vertical display panel on 1PM05J. When adjusting the controller and simultaneously reading the SEAL INJECTION FLOW indicators 4
i the operator places himself in an awkward position. This position can readily lead to a parallax problem.
I (4.9.1)(2.3.2-1) (4.5.1).
3 3.
Displays should read off-scale (not zero) when not selected, especially if zero is a possible parameter to be displ ayed. The Power Distribution panel displays do not reflect this requirement.
(4.9.2) 2 4
On 1PM05J and 1PM06J, the controls and displays required to stop the REACTOR COOLANT PUMPS in conjunction with the CENTRIFUGAL CHARGING or SAFETY INJECTION PUMPS and REACTOR COOLANT SYSTEM WIDE RANGE PRESSURE indicators (1300 psig) are not located conveniently close to one another.
(4.9.3) 1 5.
On IPM05J, switching of by-pass breakers during surveillance testing can cause operator errors.
(2.3.3.2-7) 3 6.
Functionally related controls and displays on IPM01J, Generator and Auxiliary Power panel, and on IPM02J, Turbine panel, should be rearranged so that they are vertically aligned. Consideration should also be given to demarcation lines and/or color shading.
(2.3.1-C) c 3
7.
The control-display relationship for CONTAINMENT SPRAY TRAIN A and B on IPM06J is unnecessarily ccmplex and unclear.
3 8.
On IPM0ld, Electrical Distribution panel, the normal switch position is " Auto" but there is no such indicating light.
If either MAN. TEST or MAN. EMERGENCY is selected the associated red indicator will light.
3 9.
There are several cases where displays associated with mimics, are separated from the mimics by unrelated controls,
'i e.g...on IPM01.J, ACCUM,U.LATOR, SAFETY INJECTION, and a
RESIDUAL HEAT REMGVAL display meters.
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ENCLOSURE 2 DEFICENCIES WITH PROPOSED RdSOLUTIONSTHATARE i
ACCEPTABLE TO THE HFEB t
t i
This section contains a brief description of those deficiencies
~
identified in the PDA report with resolutions, proposed by the Commonwealth Edison Company (CE), that are acceptable to the HFEB.
These items must be corrected-prior to issuance of an operating License except where otherwise noted.
m Finding
- 4. 2. 2, Neither the PA:', System nor the,
Conventional phone system have long enough cords for use at the control board.
C CE Response:
Longer cords will be installed.
Finding 4.2.3 The press to talk and channel select switches are located too low to be' ope rated ef f ectively.
CE Response:
Press to talk and channel select switches will be relocated to the slant section of the boar,d above the handset.
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t Finding
- 4. 3.'1 F'i r s t out indications occur on separate but unde"dicated panels for:
O Reactor Trip 0
Generatcr Trip
~
O Feedwater Pumps Trip The first out tiles are inte rmixed with other tiles.
CE Response:
The turbine and generator first-out a'larms will be grouped and will have Lines of demarcation to distinguish them from other alarms in their respective window boxes.
Finding 4.4.1 Two controls have deficiencies which
(
make adjustment to required level of accuracy cumbersome.
These are the M/A Station Switches and Hagen Control S t a t i on Switches.
CE Response:
These are non-critical, non-time dependent adjustments.
The problem does not warrant modi fying or replacing module.
Dust / dirt on scale windows will be removed.
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A Finding 4.4'.3 The operation of the star handle discrete rotary switches involves i
covering the discrete position labels with the operator's hand.
This could result in an erroneous setting.
CE Response:
Station wiLL review and correct all star handle discrete rotary switches.
Finding 4.4.5 100% reading on some M/A Station Switches indicate valves are 100% open; on s
others it indicates that valves are 100% closed.
This inconsistency could cause incorrect valve operation if the ope rator forgets or confuses switch characteristics.
c CE Response:
100% indication wilL be standardized to mean t h at the valve is full open.
Finding 4.4.6 The Rod Speed Linear Scale indicator increases down rather than up.
This is inconsistent with other indicators and could lead to confusion.
3-C
'I CE Response:
The Rod Speed Linear Scale indicator wiLL be changed so'that~ increases are
+
registered in the up direction and-decreases in the down direction.
Finding 4.4.7 &
The fractional rotation knobs on the 4.4.12 In-core Vertical Instrumentation panet do not conform to the plant shape code convention.
CE Response:
Th e controls are~ infrequently used, are not time critical and are not used by the operators.
Finding 4.4.8 AlL Legend pushbuttons and indicator lights are removab Le' f rom the front c
of the panel f or bulb replacemente but they are also interchangeable within a particular panel or display.
It is the re f ore possible that inadve rt ent switches wilL be made in the locations of.the pushbutton/ indicator lights when more than one bulb is replaced.
4-C s
i
~
CE Response:
Cover panels and pubhsutton/ indicator s
Lights wilL be permanently color keyed.
A matrix code util'izing colors i
displayed evidently but not prominently wilL mark the row and column of each indicator in the matrix.
t Finding 4.4.9 The EGC (ADC) Panet pushbuttons, which are contiguouse have no guards or barriers between them thereby enhancing the prospect of accidental /inadvertant c
actuation of a wrong pu s h b u t t on.-
CE Response:
Operation of indicated systems is not critical and does not create a safety c
problem if accidental actuation of pushbuttons occurs.
Finding 4.4.10 On Unit Two the Safety Injection Pumps Discharge Isolation Valve control is a keyed cont rol and the key control was mounted upside down so that the open/close positions are at 4 o' clock e
5-C'.
j f.
e i
and 8 o' clock.
The other two key controls have the open close positions at 10'o' clock and 2 o' clock.
This
~
switch is properly installed on Unit one.
9 CE Response:
This particular switch witL be properly re-installed by Unit 2 fuel load.
Finding 4.4.11 The three key controls on both Units One and Two can be operated by the same key.
,In' additions the key can be inserted and removed regardless of the switch position.
This could result in l
valves being accidentialLy le f t o'p e n or closed.
t i
CE Response:
Replace key Lock with alternative non-keylock controls or provide independent keying of keylock switches prior to fuel load.
1 Finding 4.4.12 (See' Finding 4.4.7)
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_~
e Finding 4.4.13 There is no pointer on the NIS pen l
I rotary selector switch.
CE Response:
A pointer knob will be in stalled on the NIS pen selector switch.
Finding 4.4.15 The In-Core thermocouple toggle switches do not snap into positions nor do they provide any feedback on either direction of movemen't or activation.
c CE Response:
This is a non-critical condition that does not warrant retrofit.
Finding 4.4.16 A zero to 800 pound RCS pressure C
guage by the letdown / charging system is needed for low pressure operations l
on RHR.
CE Response:
A ze'ro to 800 pound guage witL be installed, attending to human f act ors con ce rn s regarding control / display placement.
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F i n d.in g 4.4.17 The Labeling on some of the 3-way f
valves is unclear.
-l CE Response:
Labeling will be reviewed and corrected to ensure that it is consistent with valve operation.
4 Finding 4.4.18 The Tave and delta T defeat switches did not have to be pulled to actuate like the Zion Station switches.
CE Response:
Change' color of Tave and delta T defeat switches to train operator that he is removing a function from controllers.
Finding 4.4.19 On 1PM06J the handles are the same for valves with differcnt fun c t i on s.
An operator cannot differentiate wh e t'h e r a valve is throttleable, an open/
close valver or a th rottle open-seal close valve.
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i j
CE Response:
Leave open/ closed valve handles as they are.
Coat the entire projecting portion
~
of throttteable va'lve handles with white 1
j platisol or a textured sleeve material.
3 Coat just the tip of the valve handle with white plastisol for throttle open-seat cl.osed valves.
Finding 4.5.1 &
The HCV 182 controller is on the le f t 4.9.1 front diagonal panel at the bottom of the vertical display panel (1PMOSJ).
When adjusting the controller and l
^
simultaneously reading the seal injection flow indicators the operator places himself in an awkward po si t i on.
The displays and controls are not located within reasonable proximity to e f f ect - simultaneous act ion.
CE Response:
Reposition the HCV 182 controller into the proximity of the injection flow indicators and provide a dead mimic.
9-C
..~6-F i n d.i n g 4.5.3 Inconsistent type styles are evident on th e displays throughout the control 3
room.
CE Response:
Control board displays manuf;ctured by" different manufacturers use different
" type styles".
Since each " type style" is clear and legible the di f ference does not constitute a safety hazard.
The displays will not be changed to meet this guid>line.
Finding 4.5.5 Vertical metar pointer tips do not extend to within 1/16" at (but not overlap) the smallest graduat i on ma rk s "on th e scale.
Guidelines support pointer C
tips extending to within 1/16" of smallest graduation points.
s CE Response:
Potential experimental evaluation.
The problem does not appear to be severe.
Finding 4.5.6 Th e tube oil re se rvoi r linear scale
's display has no label indicating what i
being reads (e.g.,
inchese Lbs.,
percent, etc.) and scale range i s 0 t o 120. '
O.
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j CE Response:
The scale wiLL be changed to read from 0 to 100 in percent.
j
}
Finding 4.5.8 If more than four digits are required, i
they should be grouped and the groupings separated as appropriate by commas, decimal point or by an additional space.
The primary water control pre count groupings are not separated.
(6.5.5.1A3) m CE Response:
The control setting and the resultant, flow are non criticale non time dependent.
Finding 4.5.9 The bus meters have too large a scale for accuracy of required re ad i n g.
CE Response:
Consider all bus meters and install zone banding..
Finding 4.5.11 Zion Station operating experience indicated a semi gloss flourescent orange pointer on the vertical mete rs appeared to improve pointer recognition when.
presented on a white or green band background.
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- l-c l
CE Response:
Control room vertical meter pointers will be' changed from black to semi-gloss flourescent orange (#28915 j
from Federal Standard 595As colors).
~
Finding 4.5.12 Zion Station operating experience indicated that the use of a gr.een normal operating band would alert operators to abnormal conditions when the pointer was not in the appropriate range.
CE Response:
Th'e Station wilL identify normal operating ranges of meters and instruments and add green temporary transparent tape to th e surf ace of selected c
meters prior to loading fuel.
Once the temporary green banding is verified as being the correct range and helpful i
l to the operators it wiLL be permanently l
applied to the face of the meter under the pointer.
The permanent i
banding wiLL be accomplished by completion of the first r e f u e l i r. g o u t'a g e.
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Finding 4.6.1 Many controlse displays and other equipment items are untabeled.
?
1 CE Response:
Standard labels wilL be provided on I
controls and displays presently j
untabeled.
t t
Finding 4.6.2 Hierarchical and functional group L abe L in g is not presently available on the control boards or on the Remote Shutdown panel to assist the operator and to simplify the component labeling.
CE Response:
Labeling problems wilL be corrected with the devetopment and implementation of a hierarchial labeling standard.
Finding 4.6.5 &
Some of the labels and location _ aids in 4.6.7 the control room can be easily 1
l removed.
Lines of demarcation are not permanently attached.
CE Response:
The violations will be corrected.
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Finding 4. 6.'6 S'ome control board labels use inconsistent abb re v i a't i on s.
~
.i
. - l CE Response:
A standardized system of abbreviations 1
wilL be established and applied.
4 -'
4 I i Finding 4.6.7 (See Finding 4.6.5).
r Finding 4.9.1 (See Finding 4.5.1).
Finding 4.9.3 On 1PM05J and 1PM06J, the controls c
and displays required to stop the i
. Reactor Coolant Pumps in conjunction with the Centrifugal Charging or Safety Injection Pumps and Reactor'Coctant System Wide Range Pressure indicators (1300 psig.) are not located conveniently close to one another.
l CE Response:
An existing wide range pressure indicator (405) wilL be relocated to eliminate the discrepancy.
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14-C l
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