ML20004D226
| ML20004D226 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 06/02/1981 |
| From: | Tedesco R Office of Nuclear Reactor Regulation |
| To: | Tauber H DETROIT EDISON CO. |
| References | |
| NUDOCS 8106090030 | |
| Download: ML20004D226 (34) | |
Text
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UNITED STATES V
NUCLEAR REGULATORY COMMISSION
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Docket No.: 50-341 N'g Mr. Harry Tauber Vice President Engineering & Construction Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226
Dear Mr. Tauber:
(
Subject:
Requests for Additional Information in Fermi 2 Operating License Application As a result of our continuing review of the operating license application for the Enrico Fermi Atomic Power Plant Unit 2, we have developed the enclosed positions and requests for additional information. gives the results of our preliminary control room design review.
As discussed by phone previously, we will meet in Bethesda on June 3,1981 to hear your plans for correcting deficiencies. Please provide your commit-ment for correcting these deficiencies by June 5,1981.
Please amend your application to comply with the requirements listed in.
Our review schedule is based on the assumption that the additional information will be available for our review by June 8,1981.
If you wish clarification of the requests or if you cannot meet these dates, please telephone the Licensing Project Manager, L. Kintner, within 7 days after receipt of this letter.
j Sincerely, Robert L. Tedesco, Assistant Director for Licensing Division of Licensing
Enclosures:
Requests for Additional Information cc w/ enclosures:
I See next page THIS DOCUMENT CONTAINS P00R QUAUTY PAGES 8106090 Oho A
Mr. Harry Tauber Vice President Engineering & Construction Detroit Edison Company 2000 Second Avenue Detroit, Michigan 48226 cc: Eugene B. Thomas, Jr., Esq.
David E. Howell, Esq.
LeBeeuf, Lamb, Leiby & MacRae 21916 John R 1333 New Hampshire Avenue, N. W.
Hazel Park, Michigan 48030 Washington, D. C.
20036 1
Mr. Bruce Little Peter A. Marquardt, Esq.
U. S. Nuclear Regulatory Connission Co-Counsel Resident Inspector's Office Thh Detroit Edison Company 6450 W. Dixie Highway 2000 Second Avenue Newport, Michigan 48166 Detroit, Michigan 48226 Dr. Wayne Jens Mr. William J. Fahrner Detroit Edison Company Project Manager - Fermi 2 2000 Second Avenue The Detroit Edison Company Detroit, Michigan 48226 2000 Second Avenue Detroit, Michigan 48226 Mr. Larry E. Schuerman
._ Detroit. Edison. Comp.any 3331 West Big Beaver Road Troy Michigan _18084__
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e ENCLOSURE 1 HUMAN FACTORS ENGINEERING CONTROL ROOM DESIGN REVIEW / AUDIT REPORT OF ENRICO FERMI 2 DETROIT EDISON COMPANY A human factors' engineering preliminary design review of the Fermi 2 control room was performed at the site on April 27 through May 1, 1981. This design review was carried out by a team from the Human Factors Engineering Branch, Division of Human Factors Safety. This report was prepared on the basis of the HFEB's review of the applicant's Preliminary Design Assessment.and.the.
human factors: engineer.ing; design. review / audit performed at the site. The review team was assisted by human factors consultants from BioTec'hnology,-Inc.
(Falls Church, Virginia) and from Lawrence Livermore National Laboratory (University of California), Livermore, California.
Observed human factor design discrepancies were given a priority rating on 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 loading fuel and prior to achieving Jensible heat, respectively.
Priority rating 3 discrepancies should.. -
be evaluated and proposed actions reports as part of the long term design Note that some.
review (due one year from the issue date of NUREG-0{00.
priority ratings include a. superscript one '(e.g., 2 ).
Since the resolutions of these discrepancies involve relatively easy corrective actions, these dis-crepancies should be corrected prior to loading fuel).
The following sections are numbered to conform to the guidelines of the January 1981, draft' version of NUR.EG-0700 and sunT.arize the team's observa-tions of the control room design and layout of the control room operator
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interfaces with that environment.
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P'JMAN FACTORS ENGINEERING CONTROL ROOM DESIGN REVIEW AbdIT REPORT i
ENRICO FERMI - 2 NUCLEAR POWER STATION 1.
CONTROL Rn0M WORKSPACE PRIORITY
'" ' "
- m RATING FINDING 5_M' c 2
1*
When seated at the desk, the operator's view of parts of Panels 602, 603, and 604 is obstructed by the CRT and trend recorder...
2 2
The placement of controls on some panels is outside acceptable anthropometric limits.
3 3
The placement of indications on some panels is - -
outside acceptable anthropometric limits.
3 4
The recorders on Panels 808, 810, and 813 are. _ _ _. _
too high and too far back for easy reading by ; -
-; g-5th percentile persons.
1 E*
A full set of procedures is not available in the control room for operator reference.
3 6*
All of I'ie chairs in the control room do not have an adjustable-seat height.- ; a -
1 7*
The control room communication system equipment that is presently available is not physically-- -.
adjustable for individual users.
1 8'
The control room procedure binders do not.have an.
index in front of each-volume or. index-tab -
separators for. individual procedures.
1 9*
Control room procedures for both manual and.
automatic controllers are not included in the pro-cedure binders.
1 10 There are no written procedures stortc the remote shut-down panel.
Discrepancy also noted in Detroit Edison Human Factors Design Review of Enrico Fermi 2 Control Room
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WORKPLACE ENVIRONMENT PRIORITY RATING FINDING 1
1 The HVAC could not be evaluated because it was not completely installed.
3 2*
On Panel-805 the lighting on the "c" surfaces was lower than recommended. levels whereas "a".and "b2. surf aces were:w..
within an acceptable. range:::(See Fig 31) itt3 se, ii 3
3 Under some lighting conditions the contrast between indicator lights and background is low on Panel-805.
(CMC switch on surf ace. "b_"; push. button. switch. on the sloping surface "a".)
(See Fig.1) 1 4,
There are inadequate normal and emergency lighting levels on Back Panels 812 and 813, with the existing temporary system.
1 5
There is no emergency lighting available at the remote' shutdown panel.
o 3
6 It is difficult to read the CRTs on Panels:603, 804. and"'
the operator console because of low contrast caused by reflections.
3 7
There are shadows on the labels under the recorders on Panels 601, 603, 804, 805, which make them difficult to read.
1 8
The remote shutdown panel-is'not provided with---
communication.with the control rcom or-elsewhere._
1 9
The loudness of the paging system interferes with telephone conversation at the operator's. console.
3 10 On the "c" panel.of Panel-808, all recorders are too high for easy maintenance by a 5th percentile person.
The most extreme case is SUPP, CHAM. BULK WATER TEMP.
(See Fig.1) 2 11 The magnetic tag-out buttone ar/ subject to accidental.
movement and do not precluw. inadvertent operation.
I 12 Administrative. procedures for making permanent modifica....
tions to the control boards did not exist and could not be evaluated.
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ANNUNCIATORS AND AUDITORY SIGNALS PRIOT:ITY RATING FINDING 3
1*
The locations of some annunciators are not optimally placed with respect to the related controls on Panels 806 and 807.
- Fire pump alarm (D-11,12: E-11,12) are on right matrix while related controls are on left side of panel B.
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- Circulating' water pump alarms are on.. Panel-806 en -aca-tJ6 while controls are on Panel-807.
2 2
The RPF Bus 1A power failure tile F2 is not located over Div.1 React.., Prot. Syst. Pwr. Source Se1. on Pa nel-809.
21 3
Th Annunciator panels ado not have panel.identifica-tion labels.
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2 4
The single auditory alarm signal is not adequate to l
localize alarms on Panels 501, 602, 603, 804, 805.
3
~ 5*
There is no "first-out". alarm-feature provided for high priori ty alarms.
3 6*
There is no positive indication that an alarm has cleared.
3 7
Annunciator tile B-23 is inappropriately located on Panel 805 over_the condensate feedwater panel..... _..
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It should have_been located on Panel-806.
1 8* -
Some annunciator tiles which should be ~high. priority-
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amber or red are given a icw priority white color on Panel-602.
(Tile D-3) 1 8a "
Some unused tiles'with priority colors should-be- -- - -
replaced.
1 9
Inconsistent use_of_ the prjority color. codes. exists on Panel-810 where alarms having similar priorities use different colors.
(0-11 i s amber, C-10 is white)
I Given the ease of the corrective action involved relative to the I
potenti.1 for improving operator performance, we recommend that these items be addressed and corrected prior to loading fuel.
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ANNUNCIATORS AND AUDITORY SIGNALS PRIORITY RATING FINDING 3
10*
On Panels P809 and P810, Auto Close Annunciators are in same groupings as the Trouble Alarms.
2 11 The wording of " East" and " West" Turbine tiles on Panel-805 is inconsistent with the< wording on the,r. no un,v
" North" and " South" Turbine tiles ur(TilestC-3, ITile; t-3.
C-4,D-3) 1 12*
The blue-tiles on Panels 601, 602, and 806 are difficult to read whether lit or unit t...This is...
caused by " wavy" cellophane and glare.
(Panel-601, D-3, 0-4; Panel-602, 0-5, D-6, 0-7; Panel-806, F-4, F-5) 3 13*
The annunciator on Panel-810 includes multiple inputs ' 7-.
to a single tile.
Individual breaker tiles would pre-vent an unnecessary alarm when a breaker is scheduled out of service.s -
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3 14 Tile D-9 on Panel-601, alarms to~ indicate an ADS tm -
Safety Valve. leak. The temperature recorder is in the relay room but there is no reference to the loca -- - -
tion of the leak on the panel. The location of the leak must be determined by the temperature recorders __
located in the relay room.
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15*
There is no index.readily available which will direct an operator from an alarm to the correct response procedure.
3 16 There is no positive means available to indicate to an operator when.an. alarm.is out of_ service.. Push buttons on the panel at the-side of-Panel-601 allow-"+
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selection and indication of tiles. removed from...
service; but the panel does not cover all alarms, and is not ' considered easy to recognize. o..:_
3 17 There is no auditory annunciator signal. code which differentiates an alarm from an alert.
1 18 The evacuation signal system was not connected and could not be evaluated..
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ANNUNCIATORS AND AUDITORY SIGNALS PRIORITY RATING _
FINDING 1
19 The annunciator alarm audio levels relative to the normal ambient noise level could not be measured because of the temporary status of the ventilation system and control room floor.
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CONTROLS PRIORITY RATING FINDING l
1 1
The locations and shape of the controls for the annunciators on the front of the board make them subject to incorrect selection and operation when the operator is looking at the annunciato-t.
3 23 There are no covers:to prevent dirt from; falling :ren ;21tinu into openings left wher 'andles are removed from switches on Panel 810.
(65F bus)
The removed handle was hung on another handle.
2 3*
Some control switches do not move in the perferred direction for control action vs function; i.e.,
Clockwise f or " raise", "on", " increase", and Counterclockwise for "l ower", "of f", "decreas?".
Inese discrepancies exist on Panels-603, 804, 808, 809.. B10, 817.
2 4*,
Switch handles tend to obscure the switch label on....
Panel-812, (B11) and Panel-805- (Tachometer select). -
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1 5*
The Panel-601 Relief Valve position indication uses the valve solenoid excitation instead of a positive--- -- ----
position indicator.
1 6
The arrows on several switches on Panel-808 point beta >een the mode being_ selected.e._
1 7
The push button switches on Panel-805 'and 806, which --
are protected with a plastic cover,. do not have black.... q-side borders. The unprotected switches located else-where djt ave black side borders.
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8 On the Remote: Shutdown-Panel.
- The push button switches.do not have black side borders as do similar switches located elsewhere.
(RCIC Turbine Control Valve,..CIC Steam Inlet Valves, etc.)
- The indicators do not have white side borders as do similar switches located elsewhere.
1 9
The " Slow" and " Fast" label is missing from the Full Flow Valve Switch (H-301,8-F-608) on Panel-804..
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. 4.
CONTROLS PRIORITY RATING FINDING 1
10 The position indicator itne on the Reactor Feed Pump Turbine North Trip switch on Panel-805 is not visible.
1 11 Four black reset buttons on Panel-601 violate the green reset button color code..,..(ADS Initiation. Dry- -
well High Pressure,., ADS Div.1. J;imere logic, ADS.Div. 2:..,
Timer Logic, Inboard MSIY -Isolation)-
2 12 The color code of the IRM recorder pens and the IRM scale selector switch position lines on Panel 603 is not consistent.
3 13 The tooth down key operated switch (Scram Discharge Volume Hi H 0 Level Bypass) on Panel-603 violates the '
2
" tooth uy_ plant convention position for key operated swi tches..
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VISUAL DISPLAYS PRIORITY RATING FINDING 2
1*
It is difficult to tell the difference between the "on" and "off" condition of the blue " power on" indicators used on Panels 809 and 810.
3 2*
i Inappropriate ~. scales. exist on:some: meters, as + ::sf;.-e; follows:
icite s:
Panel-602
- Drywell Pressure is scaled in " inches of H 0".
- EECSW Hx flow _is_ scaled.in percent..
- Post Accident Reactor Pressure is in " inches of Hgo
- Diesel Service Water Flow is scaled in percent.
Panel-603 Coreplate d/p is scaled in percent.
- Start up Line is scaled in percent.
Panel-804
- -0L~
2 cooler temperiture u,es a decimal scale 'bd a?.<cale e.nd
- H multiplier, which'is not recommended. --
Condenser Vacuum is sealed in " psia",- but the trips --
are known in " Inches of Hg".
Panel-o08
- SGTS flow is scaled in percent
- Turbine Building Atmosphere d/p is scaled 'in per- - -
cent.
- Reactor Building: Control-Cente:--d/priscscaled-in r
w percent 2
3 No scales exist on_some meters _ as fol. low:
- Drywell Pumps-level. - n a 4 A4
- Steam flow HED.
1 4
The RHR Exchanger A level control'.and. Pressure.
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Control meter on Panel 601 does not indicate units on percent scale.
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3 5
A meter scale on Panel-806 that reads "lbs. per sq. in." does not clearly label that the pressures indicated are negative value.
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5.
VISUAL DISPLAYS PRIORITY RATING FINDING 1
'6*
Several scaling problems exist on Panel-602.
- Wide range water level scale is incorrect.
- HPCI suction and discharge pressure use same scale.
(suction pressure will be pegged low when operating.) 2;u.:. n u n
- Scale limits are not numbered for Post: Accident es a.cior.t Reactor and Torus level.
3 7*
In several cases the number of scale graduations between numbers _is greater.than the_ recommended 9.____.
(Panel s 603, 807, 810, 811, 816.) Unit graduations in some cases are not 1, 2, or 5 divisions.
1 8
The scale is missing on the "Interruptable Control Air" meter. --
1 9
There are no unit markings on the RCP and Oil Cooler temperature controlle r indicator. scales.._ _. _ __....
2 10**
Many' meters / displays on various panels.do.not havec da ;. 2 :_ o normal, lower, or upper operating limit range mark -
ings.
3 11*
The Casing Gas.. Purity indicator on Panel-804 moves in a direction opposite to that recommended.
1 12 The.. indicator lights for the EDG 11,12,13, and 14 local controls have inconsistent color-coding.-- -----
- EDG 11 and ~127 uses all whiter... '.
- EDG 13 uses red, blue-white, red
- EDT 14 uses white, blue-white, white.
1 13*'
Some" inconsistent use 'of: color codes art:--
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- On fire protection Pa.nel-816, the " fire" light colors are not consistent,- being' blue in the "b" section and white on the "a" section." Blue is also used on the adjacent Panel-807 to indicate
" bus energized".
- Or. turbine and FW control Panel-804, the mimic color for HD turbine exhaust steam is not con-sistent with the azure green Fermi-2 color code.
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VISUAL DISP 1.AYS PRIORITY RATING FINDING 3
14 The color coding of the vertical illuminated mimic display (RHRS) on Panel-601 is not consist-ent with the color coding of the mimic displays of i
the associated systems (RCIC).....
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PANEL LAYOUT PRIORITY RATING FINDING 3
1 The main turbine shaft vibration recorder group -
would be more useful if relocated to front of Panel-804.
3 2-Some of the controls of-the recircr pumps on: Panel.,,. nn ranei 603 are mirrored. re mier., ed.
21 3
Recire. pump B needs dei.urcation from the reactor feed pump on Panel-804.
21' 4
Demarcation lines are needed to group controls and indicators into smaller blocks on the back of Panel-805.
3 5
The switched 480 volt bus voltmeters are not located consistently with respect to the buses on Panel-809 and Panel-810 and should be separated by some kind '-
of demarcation...
2.
3
'6 7
An air alarm at Panel-807 requires -the operato to sas u*ae b$
activate CMC on Panel-601 and' Panel-602 and then -
return to Panel-807 to control air compressor-CMC.
3 7
The thumbwheel and push-button controls for the CRT display are located within the Drain Systems mimic on Panel-804...;-
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CONTROL / DISPLAY INTEGRATION PRIORITY RATING FINDING 2
1 The fire zone indication on Panel-816 gives no location information.
3 2
The tank dump valves on Panel-816 are not positioned i n numerical order...-(i.e.,.-3,: 4, l ~.2)
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Verification of scram reset requires an-operator-to leave Panel-603 and go to the relay room.
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3 4
The annunciator for the' hydrogen recombiner is located to the far left of Panel-808 while the-~~
sociated controls are to the far right.
2 5
It is not clear what the no ficw warning between the first and second CMC switches for the battery room a/c-exhaust system is indicating on Panel-808.
3 6
Leak detectors on Panel-601 are numbered 1 through 8 without any indication of the-location ofithe.leah m t.c tst 3
,7 It is not clear which controls are related to which =.:.:n t 4 indicators for the RFPT North Turning Gear on l
Panel-805.
3 8
The breaker trip annunciator trip tiles for bus 72J and 72K are on Panel-810 while the associated controls _.....
are on Panel-809.
3 10 -
The recorders.for the-chlorinat. ion and.seryice water---------.
levels are inverted with respect to their associated controls on Panel-807.
3 11 The IRM recorders and-range-switches;on: Panel-603 -- ::: c:--;i are arranged in an unconventional X pattern rather than a vertical pattern.
2 12 The EDG control on Panel-809 and Panel-810 turns left to raise while the indicator moves clockwise.
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13 The turbine building exhaust fans select switches on Panel-808 do not clearly indicate the relationship between the exhaust fans and supply fans.
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CONTROL / DISPLAY INTEGRATION PRIOR 11Y l
RATING FINDING 2
14 There are two different closed indicators on supp.
chamber vacuum display - one for fully closed and the other for partially closed - without an indica-tion of which.is which.
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LABELS PRIORITY RATING FINDING 1
1 There is a two scale meter with one pointer for the off-gas PRMS, on the back of Panel-601, without an indication of which scale the arrow is using.
Units are not indicated on the PRMS recorder scale on : + wuo 1
2 2 the back of Panel:-601.d u s1 Jul.
1 3
The jack plugs on the back of Panel-601 are labeled with ink rather than a pennanent label.__......
1 4*
The throttle valves on Panels 601 and 602 (Outboard Isolation Valve F005 A) do not have a distinct valve type designation.
21 5
On Panel-602, the label for the Headspray Inboard Isolation Valve (FO-22) is misplaced and is located under a mimic flow path below the Containment Spray- -
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31 6* ~'
System designation is. not shown en instrument bame ':---d. :----
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plates on Panel-602.
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31 7
Labels on Panel-602 and Panel-804,have both black on white and white on black.
31 8*
There is a lack.of group demarcation.in.the. mimic
.: : c display of the PHIC on Panel-602...
7.
9*
The labels of the recorders on Panel-603 tend-to be --.---...;.-
obscured by the overhang.
1 10 The label for '!in"-and "out"- motion is-mi ssing - on. - -.
the " Rod Out Notch Override"--switch -on-Panel-603.=
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11 There is no label to.descr.ibe the. function of the meter group on Panel-603.
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31 12 Labeling for similar parameters on Panel-603 is in-consistent (i.e... recire, vs recifculation; FW vs_
1 13 There is no label on the Turbine Overspeed -Trip-toggle switch on Panel-804.-- ' -
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l 8.
LABELS PRIORITY RATING FINDING 1
14*
The Panel-804 keylock labels are above the switch while they should be below to be consistent with plant convention. Also position indication is missing.
2 15 ?
The11abels ofTthe: recorders.oo P-805 tend.to.be.o eia no eu obscured by the overhang.
31 16 Labels for center, north,, and south feedwater. heater level s on Panel-805 are confusing.....__.. _.
3 17 Valve symbols used are not consistant on the con-den mimic on Panel-805.
1 18
- There are incorrect labels for valves on Panel-805.
1 19 The NM CNDR vacuum normal range pressure label does -
not match the..me ter scal e. on. Panel-805. ____..___.._
Borders that differentiate controls:from indicators, inriicate i
3
20 are not consistantly placed on Panel-808, i.e.,-some c are located above and below-rather than to the left.- -
and right.
I 3
21 Hierarchical labeling is not used on EDG for the-group on Panel-808/ _
1 22 The labels are incorrect-for-CMC-switches for Battery-r~--e -
Room a/c-Exhaust System on Panel-808.
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23 Some labels on the mimics and meters on Panel-809 are incorrect.
1 24*
Some switch positions are either temporary or not labeled.
- Panel-811 - Brownstown 3 Li ne Pha~se Selector r.-
--- sc-- -
Brownstown 2 LN ihase Selector 4
(Note inconsistent labeling of "LN " vs "Line".)
- Panel-812 - 72E, 72F, 480V Bot Se1.
72W, 72N, 480V Bus Se1.
3 25 The contrast between lettering and background on back-lighted push button switches. in inadequate on Panel-811.
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LABELS PRIORITY RATING FINDING 1
~26 The primary containment atmospheric radiation monitoring system on Panel-812 has no indication of which pen records which parameter.
31 27*
The'1abel " Filter Fire""on Panel-812 is not u -
mn sufficiently. descriptive. Ac:crf orfve-1 28 The resin and "solka-floc" switches on Panel-816 have no label on covers.
31 29 Labels on CO2 systems switches on Panel-816 are not clear.
31 30*
Hierarchical labeling could be used effectively on Panel-816.
Demarcation lines on Panek-816 are easily dislodged.
3 31 1
32 The; fire labels,on: Panel-816 are blue on':the. level B- :
indicators while ' they are 9hite'.on the level A - ir :' a indicators.
1 33 Switches on Panel-816 have no indication of what com-ponent is being control. led.;
31 34*
Lines of demarcation are-not used-to-separate _the control matrix on Panel-817.
.1 35 The indicators and controls for the RCIC turbine '
control valve and other valves on the Remote Shut-
~
down panel do not line up with the mimic symbols and are without labels.-..n w
3 36 The. same color codes are used on mimics to indicate several different functions.
3 37 The lighted mimic on Panel-601 does not use the same color coding as corresponding mimics on sub panel s.
4
. 8.
LABELS PRIORITY RATING FINDING 3
38 There is ar inconsistent use of track widths to indicate primary and secondary flow paths on the Panel-601 mimic.
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39.
The mimic flow _ arrows are not distinct on Panel-601.
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40 '
Color: codes on.the steam supply. mimic _on; Panel-804_cr. ? nal-S' are inconsistent.
3 41*-
The mimic on Panel-804 should show starting and end.-
points.
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42*
There are inconsistencies in the mimic colors for
" Main Steam From Control Valve", which should be moss
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i grec7 and the turbine shaft..which should not be j
the A ae color as the steam on Panel-804.
2 43 There are many instances where the flow directions, indicated on the mimic on Panels _805:and_808, are.... -...,,n-b missing or incorrect.,. '
3 44 Mimic components on. Panel-805 are not always tied to the mimic lines.
3 45 The gray mimic. lines on Panel-805 are in poor con...
trast with the green panel background.
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46 Thera.are mimic lines missing on. Panel-805.
3 47 The initiation and termination points.of the mimic.7
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on Panels 804,.805,- and 806 should all..be labeled l
and should be consistent.
31 48 The reactor feed pumps'and related displays on Panel-805 a offset and-therefore. should have de.- -_
marcation '.ines.
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49*
Porti6ns of the mimic on Panel-805 are missing.
2 50 Thg relstionship between.the.[Klind_SWGR supply /
exhaust fans on Panel-808 is unclear, and mimic or demarcation lines are needed.
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LABELS 1
PRIORITY RATING FINDING 3
51 Mimics on Panel-809 and Panel-816 should show fl6w:
directions.
3I 52 The EDG controls should be distinguished from the mimic on Panel-809, 3
53 ?
Arrows indicating directiont of flow should.'be' added, d.! ' g.2 where appropriate, to the mimic on Panel-809.
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54 There are unlabeled.end points on the mimic on the - r-remote shutdown panel...
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PROCESS COMPUTER PRIORITY RATING FINDINI.
1 1
The sof tware was not available to review the command language.
2 2.
The operators keyboard combines a standard QWERTY..
keyboard with function keys; --
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The numeric keyboards are not pushbutton telephone 3
layout.
2 4* -
CRT di splay items are identified by. log number,, ratherm..
than by system or program name.
1 5
The CRT control console has temporary labels.
3 6*
There is no Fermi 2 unique color standard for CRT di spl ays.
3 72 The bottom oft.the. screen: on; Pan _el-804 is not visibler 4.n.-
to a 5th percentilb. ope rator.':
2 8
The number of significant digits displayed in CRT data is not consistent with instrument accuracy.
2 9.
The decimal point on CRT displays is not right 'or left justified in a standard format.
The computer CRT output is 12b characters per second 1
10 which is too slow for the 3001pm line printer.
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10.
DATA RECORDING o
PRIORITY RATING FINDING 1
1*
The alarm points are not identified on recorder scales.
1 2*
All panels with recorders did not have the recorder scales marked with-the normal.or. abnormal, safe-orr-,;,
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i unsafe, or expected or unexpected: range.;r:::e. rance.
2 3
The scale lengths on some recorders differ from the paper scale.....
The multipoint recorders use more than four c'olors, 3
4 have as many as 20 channels, and are hard to differ-entiate.
21 5 -
The reactor core differential pressure. recorder uses a percent scale rather than absolute units..
3 6
Many recorders.do not.have, frosted glass covers and reflection can be-a problem.--
21 7
The Drywell and Torus Air and k'ater T.wperature recorders on Panel-601 and Panel-602 Lave-inconsist --..--
ent labels.
21 8
The Pressure ' recorders on Panel-602 have obscured -- --~~
scales when the face is closed.
o 21 9
On many recorders there is no ind'ication of unitst---
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The 12 point recorders on Panel-816 use two sets of l
six colors and are difficult to read.
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11 Ther recorders on Panel-602 have different: scales #r t..u-~
on the same recorder. Paper can only match one scale.
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. HUMAN FACTORS STRENGTHS OBSERVED......
The control / display integration. on all panels is very.' good and is, particularly good for the ECCS system.
Good use was made of push button valve controls and indicator lights to verify control position.
The use of color-coded, multi ~ple position switches was go'od.
The lighting capability in the control room is generally very good.
The maintenance. tagging procedures.used helped avoid clutter on.the.contro.1 -
panels; however.. some means of avoiding)inadvertant activation of-contro
.--#+.,3 (e.g., a strip of tape over:the control would. improve the. procedure.Se crocee..r~.
The mimic layouts were gener' ally very good, showing system functions and system sequence of operation.... ___, m Generally, the location of the annunciators and the intelligibility of the -
wording were good.
Most labels were clear and easy to ';rderstand.
.The majority of the components on the control boards were well located and -
within acceptable anthropometric limits.
The capability,to switch to-the remote, shutdown panel without.. concern..for.. :..;. m valve position ' settings -in the.controh room,was. very good.
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Almost all controls and. indicators were located on the main panels without...
i causing overloading.
The avoidance of excessive. use of abbreviations made labels easy to read and. - %
m interpr et.
SYSTEMS THAT COULD NOT BE -EVALUATED --
Temperature, humidit.y and ambient noise level could not be evaluated because --
the permanent HV AC system was not installed.
Administrative p rocedures-for-making-permanent modifications. to ther control s..
s.,
boards did not exist.
l Most software was not available for review.-
There was no record of the standard color code scheme.
The control room emergency evacuation alarm was not oper le.
The following sections are numbered to conform to the guidelines of the January,1981, draft version of NUREG-0700 and summarize the team's observa -- - -- -
tions of the control room design and layout and of the control-room operatois' interface with the control room environment.
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ENCLOSURE 2 REQUESTS FOR ADDITIONAL INFORMATION IN THE SAFETY REVIEW ENRICO FERMI ATOMIC POWER PLANT UNIT 2 DOCKET NO. 50-341 Requests by the following branches in NRC are included in this enclosure.
Requests and pages are numbered sequentially with respect to previously transmitted requests.
Branch Page No.
Mechanical Engineering Branch 110-15 Reactor Systems Branch 212-55 212-56 Power Systems Branch 222-53 through 222-57 i
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e 110-15 110.0 Mechanical Engineering Branch 110.20 Provide the following information used in the design of the Fermi 2 safety relief valve (SRV) piping:
a) The latest SRV hydraulic transient time history loads generated in the SRV piping due to the imbalanced pressure waves resulting from an SRV actuation. Also, include the latest time history loads due to the discharge of the water column from the submerged piping and quencher device.
l b) Provide a tabulation of the loads (forces) used for the interim design of the supports of the SRV piping inside the torus wetwell.
c) Re-evaluate the adequacy of the SRV piping and supports inside the torus wetwell for the latest SRV hydraulic pressure transient and water slug loads. The re-evaluation should consider the comoination of normal, SRV, LOCA, and seismic loads using the response combination method provided in NUREG-0484 Revision 1.
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212-55 212.69A Since the initial discovery of cracking in boiling water reactor (Bh'R)
(4.6) control rod drive return line (CRDRL) nozzles, General Electric (CE) has proposed a number of solutions to the problem. One solution GE has proposed is a system modification that involves total removal of the CRDRL and cutting and capping of the CRDRL nozzle.
From your response to Q212.69. Enrico Fermi-2 plans this modification. Address the applicable items and staff concerns specified in the letter from D. Eisenhut, NRC, to R. Gridley, GE, dated January 28, 1980, on the subject of control rod drive return line (CRDRL) removal and capping CRDRL nozzles.
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212-56 212.0 REACTOR SYSTEMS BRANCH 212.182 Calculations of NPSH available to ECCS pumps in BWRs are normally provided with reference to the pump suction. We are concerned that under certain post accident conditions the potential may exist for damage to ECCS pumps from cavitation because of local flashing in the system suction lines. The potential can result for example from local elevation changes in the piping runs. Calculations of NpSH available it the' pump suction may erroneously assume liquid continuity up to the point of pump suction. We require therefore that the applicants provide calculations demonstrating that all points in all safety related suction piping, the NPSH available is adequate to preclude local flashing under the worst postu-lated conditions.
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222.55 The FSAR text and Table 3.2-1 states that the components and piping systems (3.2)
(9.5.4) for the diesel generator auxiliaries (fuel oil system, cooling water, (9.2.5)
(9.5,6) lubrication, air starting, and intake and ce4ustion system) that are mounted
'9.5.7)
(9.5.8) on the auxiliary skidt are designed seismic Category I and are ASME Section III Class. 3 qual.ity. The engine mounted components,and piping are designed and manufactured to DEFA standards, and are seismic Category I.
This is not in accordance with Regulatory Guide 1,26 which requires the entire diesel generator puxiliary systems be designed to ASME Sect. ion III Class 3 or Quality Group C.
Provide the industry standards that were used in the design, man ~ufacture, and inspection of the engine mounted piping and components. Also show on the appropriate P&ID's where the Quality Group Classification changes from Duality Group C.
222.56 '
You state in section 9.5.5.2 each diesel engine cooling water system
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(9.5.5) is provided with an expansion tank to provide for system expansion and for venting air from the system.
In addition to the item leaks l
mentioned.,the expansion tank is to provide for minor system at pump ihaft seals, valve stems and other components, and to maintain required NPSH on the syster circulating pump.
Provide i
the size of the expansion tank and location.
Demonstrate by analysis that the expansion tank size will be adequate to maintain required l
l pump NPSH and make up water for seven days continuous operation of the diesel engJne at full rated load without makeup, or provide a seismic Category I, safety class 3 make up water supply to the ex-pansion tank.
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1 222-54 222.57 For the diesel engine lubrication system in tection 9.5.7 describetheprotect-l (9.5.7)
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Teatures (such as blowout panels) provided to prevent unacceptable crankcase explosion and to mitigat'e the consequences of such an event; 222.58 Describe the instrumentation, controls, sensors and alarms provided in (9.5.8) the desip of the diesel engine combustion air intake and exhaust system which alert the operator when parameters exceed ranges recommended by the engine manufacturer and describe any operator action required during 1
alarm conditions to prevent harmful effects to the diesel engine.
t Dist.uss systems interlocks provided.. Revise your FSAR accordingly.
(SRP 9.5.8, Part III, item 1 & 4)..
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222.59 Provide the results of an analysis that demonstrates that the function (9.5.8) of your diesel engine air intake and exhaust system design will not be j
degraded to, an extent which prevents developing full engine rated power or cause engine shutdown as a consequence of any' meteorological or accident condition.
Include in your discussion the po'tential and effect of fire extinguishing (gaseous) medium, recirculation of diesel combustion products, or other gases that may intentionally or accidentally be released on site, on the performance of the diesel generator.
(SRP 9.5.8, Part III, item 3).
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222.60.
41scuss the provisions madi in your design of the diesel engine combustion (9.5.8) f
. air intake and exhaust systs to prevent possible clogging, durirG 5tandby and fn operation, from abnormai cifmatic conditions (heavy rain, freezing rain, dust storms, ice and snow) that could prevent operation of the diesel j
generator on demand.
(SRP 9.5.8, Part III, item 5).
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222-E5 Show by analysis thst a patentisi fire jp_ths. diesel generator build-222.61 (9.5,8) ing together trith a single failure of the fire protection syste= will not degrade the quality of the diesel ccc6ustion air so that the remaining diesel will be able to provide full rated power.
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222-56 222.62 The FSAR text and Table 3.2-1 states that the components and piping systems (3.2)
(9.5.4) for the diesel generator auxiliaries (fuel oil system, cooling water, (9.5.5)
(9.5.6) lubricaticn, air starting, and intake and combustion system) that are (9.5.7)
(9.5.8) mounted on the auxiliary skids are designed seismic Category I and are ASME Section III Class 2 quality.
Figures 9.5.2 and 9.5.3 show certain lines for these systems as being designed nonseismic and Quality Group D.
Text, table and drawings seem to be in conflict, clarify this Oiscrepancy, and in particular for the following items provide the requested information and/or comply with the stated positions:
a.
In Figure 9.5.2 the diesel oil storage tank fill and vent lines are shown as non-seismic, Quality Group D piping. This is unacceptable.
These lines are necessary for continued emergency diesel engine operation and should be designed seismic Category I, Quality Group C.
Comply with l
this position.
b.
In Figure 9.5-2 Sheets 1 and 3 show the clean fuel drain lines from the injector nozzles and dirty fuel drain lines as being designed non-seismic Quality Group D.
It is unclear from the figure and the FSAR text the purpose of these lines.
Provide a discussion on the purpose of the lines and to where they are routed.
If they are used during engine operation they should be designed seismic Category I, Quality Group C.
Comply with this position.
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222-57 c.
Figure 9.5-2 shows a lube oil tank and connecting lines to the diesel generator as non-seismic, Quality Group D.
The FSAR text states that the tank is used to replenish lube oil to the enigne sump during engine operation. A seismic event would result in the spillage of lube oil in all diesel generator rooms causing a fire hazard. The tank and associated lines seem to be used during engine operation. Therefore, the lines should be designed seismic Category I, Quality Group C.
Comply with this position, andprovide lube oil tank capacity and location.
d.
Figure 9.5-3 shows the jacket coolant water system vent lines (two) and the equalizing line to the expansion tank as non-seismic, Quality Group D., This is unacceptable. A seismic event would result in the loss of water to all diesel generators. These lines are necessary for continued emergency diesel engine operation and should be designed seismic Category I, Quality Group C.
Comply with this position.
e.
Figure 9.5-3 shows the diesel engine exhaust lires as non-seismic Quality Group D.
This is unacceptable. The exhaust system should be de::1gned seismic Category I, Quality Group C.
Comply with this position or provide justification for non-compliance.
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