ML20113D511
| ML20113D511 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/08/1985 |
| From: | Fiedler P GENERAL PUBLIC UTILITIES CORP. |
| To: | Thompson H Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 NUDOCS 8504150334 | |
| Download: ML20113D511 (37) | |
Text
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GPU Nuclear Corporation NUOIME 100 Interpace Parkway Parsippany, New Jersey 07054-1149 (201)263-6500 TELEX 136-482 Writer's Direct Dial Number:
April 8,1985 Mr. H. Thompson, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Thompson:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Supplement 1 to NUREG 0737 Detailed Control Room Design Review (CRDR)
Supplement to the Summary Report
Reference:
Letter dated April 30, 1984, P. B. Fiedler to D. G.
Eisenhut In accordance with NUREG-0737 Supplement 1, the Oyster Creek CRDR Summary Report was submitted to the NRC on April 30, 1984. The report was subsequently reviewed by the NRC and its contractor; and, as a result i
meetings with GPUN were held on November 1 and 2, 1984 in Washington, D.
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C. and on November 28, 1984 at the Oyster Creek Station. The enclosed supplementary report provides additional information to clarify the CRDR Summary Report as well as other supportive information.
In previous discussions with you and members of your staff, GPUN has stated we are currently reviewing the Cycle 11 outage workscope as part of our long range planning effort.
Please be advised that upon completion, schedular extensions may be requested for certain commitments contained in this submittal.
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GPU Nuclear Corporation is a subsidiary of General Pubhc Utihties Corporation L
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2-Should you have any questions, please contact the Oyster Creek Licensing Manager at (609) 971-4643.
Very truly yours, A
Vice' President and Director Oyster Creek 1r/1432f cc: Administrator Region I U.S. Nuclear Regulatory Connission 631 Park Avenue King of Prussia, Pa.
19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, N. J.
08731 1
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Supplement to the Summary Report on the Oyster. Creek Control-Room Design Review I.--
Introduction and-Background On April 30, 1984 the Oyster Creek. Control Room Design Review (CRDR)
Summary Report was submitted to the NRC in compliance with require-ments of NUREG-0737 Supplement 1.
This report was subsequently re-viewed by the'NRC staff and its. contractors and meetings were held on November 1 and 2, 1984 in_ Washington D.C.' and on November 28, 1984 at' the Oyster Creek Station to review records of the review, answer ques-tions of the reviewers and audit some of the deficiencies noted in the
-report by viewing arrangements in the control room. Due to the summary nature of the report, details of many of the deficiencies identified were not available and a review of the records and dis-cussion with the participants was helpful in determining the adequacy of the CRDR.
-This supplementary report provides additional information to clarify the Summary Report. The remaining sections of this report provide (1)
Schedules for items listed in corrective action section of the Summary Report which required further evaluation or selection of various alternatives before final implementation; (2) A program plan for the implementation'of revision 3 of the BWR Emergency Procedure Guidelines (EPG's) which includes task analysis of control room interfaces; (3) A description of the use of computer driven CRT displays to correct Human Engineering Deficiencies (HED's).
II.
_ Supplementary-Schedule Information A number of the deficiencies identified during the review were of a nature that either'(1) further evaluation was necessary to determine if corrective action was necessary or (2) several alternates of cor-rective actions were identified which could all adequately correct the finding. For both these cases the description of corrective. actions indicated evaluation or consideration ~of alternatives and this section clarifies the schedule to complete these evaluations. The following list is keyed to the groups number of Table V-I of the summary report.
with the sequence number in each group indicated. As an example item 3-15 is the fifteenth deficiency in group 3.
An update Table V-I has also been attached with this information.
L Group 1 - Further evaluation required s.r l'
l-1
.The density compensation study will be completed in 1985.
l-2.The core region instrument was modified and tested. Periodic l
surveillance tests will be used instead of continuing operations with pumps running.
Item.is complete.
1-3 Modifications to add indications are scheduled over the next two l:
refueling outages.
l-4 Study to be performed in 1985 j
1-5 Study to be performed in 1985
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' 1-6 Study to be performed in 1985
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1.7 ' Rod Worth Minimizer engineering is ongoing to. support portions
'of system modifications in next refueling outage with total-7 project to'be completed in second refueling outage;. scope of project includes new display design.
1-8 Study to be performed in 1985 1-9 Study to be performed in'1985 1-10 Study to be performed in-1985 1-11 ' Study to be performed in 1985 1-12. Study to be performed in 1985 1-13 Study to be performed in 1985 1-14 Evaluation to be performed during panel modification engineering to be completed in 1985.
1-151 Evaluation to be performed during panel modification engineering to be completed in'1985.
1-16 Recorder evaluation underway to be completed in 1985.
. Group 2 - Relabeling and Demarcation 2-21 Evaluation to be performed during panel modification engineering to be completed in 1985.
1 2-42 The engineering of panel. modifications' includes a program to evaluate and improve all display scale graduation and labels.
Some meters are too small to allow any improvement in these cases an evaluation will be completed which determines whether present display:is adequate or requires replacement with a different instrument. Evaluation to be completed in 1985.
2-49_ All indicator lights will be evaluated and those. determined to
_ be deficient will be changed to industry standards. Schedule to be determined after evaluation.
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2-55 Standard specification for new labels specifies low glare Gravoply II labels; the only exception are those cases which are photo-engraved metal pl.ates.
2-56 Evaluation to be completed in 1985 2-66 Same as 2-21.
.2-67 Same as 2-21 2-69 Same as 2 2 Same as 2-21. Major electrical system modification will;take
" place _in second refueling outage at which time changes to electrical system panel arrangement are scheduled.
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2-71 Same as 2-21 2 74 Same as 2-21 c
2-75 A list of indications being evaluated for volume to level information labels are:
Isolation condensers, reactor level, hotwell level, condensate storage tank, drain tanks and torus.
Group 3 - Administrative 3-1, 3 Review of design data and plant startup test' data alleviated and 3-4 concerns for these deficiencies.
Items complete.
3-9 Shift assistants have been assigned which resolve administrative burden as much as possible under present regulations. This item is complete.
- 3-15 It is a goal of the operations d,epartment to provide three CR0's per shift, however, the presence ~of this operator is not mandatory for emergency _ operations.
Group 4 - Hardware 4-8, 4-9, These items refer to a consolidated display as corrective action.
4-10,- 4-16 Many of these findings could be corrected by individual improve-4-18, 4-41 ments to the displays, but and integrated solution appears to be 4-42,.4-44 the_best alternative. The proposed solution is a con 6ptual 4-48, 4-56 ' grouping of parameters on a single location visible from differ-4-66 ent places in the control room. Evaluation of designs to correct the deficiencies will be completed in 1985. Portions of displays which are supported by projects in present outage will be installed in next outage. Final installation will occur in second outage.
4-17 Evaluation of alarms will be completed in 1985.
4-35 Selection of displays to be interchanged will be completed in 1985 in time to support work in next refueling outage.
4 Recorder study will be completed in 1985.
4-39 Recorder study will be-completed in 1985.
4-40 Some improvements have been completed. Replacement of broken /
missing labels is complete. Repainting of most frequently used s
control room panels is scheduled for next outage.
4-43 Evaluation will be completed in 1985.
4-45 Moving lights to front panel will fulfill confirmation function
~~and eliminate mistaking a burned out light for a de-energized solenoid by the prominent positioning.
If evaluations show lights do not need to be moved, the burnt out lightbulb problem will be addressed sepa'rately.
4-51 Reevaluation has shown that information is useful to operators and will be examined by labeling and demarcation modifications planned.. No meters will be removed, item is complete.
4-57 Evaluation will be completed in 1985.
4-58 This item will be' included in recorder evaluation to be com-pleted in 1985.
4-59 Evaluation to be performed during panel modification engineering to be completed in 1985.
4-60 Evaluation to be performed during panel modification engineering to be completed in 1985.
4-61 Evaluation to be performed during panel modification engineering to be completed in 1985.
4 Evaluation to be performed during panel modification engineering to be completed in 1985.
4-63 Evaluation to be performed during panel modification engineering to be completed in 1985.
4-64 Evaluation to be performed during panel modification engineering to be completed in 1985.
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Group 5 - Computer Placement of deficiencies in this group is explained in Section IV of this report. Evaluation of these findings will be completed on a schedule to support installation in accordance with schedule category 3.
Group 6 - CR Environment 6-7 Evaluation will be completed in time to support installation by schedule category 3.
6-10 Humidity study will be completed in 1985.
6-12 -Same as 6-7.
III.
Implementation of-Revision 3 of BWR EPG's The present revision of the EPG's implemented as Emergency Operating Procedures at Oyster Creek do not include the revision 3 Secondary Containment or Radiation Control guidelines.
It is the intent of the plant operating staff to implement these guidelines into plant procedures during the next refueling. outage presently scheduled to commence in late 1985. This procedure revision is of such a magnitude to require special review of both the procedure format and useability and the characteristics of the control room as they affect the useability of the procedures.
The following elements of review are planned prior to implementation of this revision of the EPG's:
(1) A review of the operator functions and tasks for each step of the procedure which will establish control and display requirements to carry out each step. This review will also establish the specific characteristics of the controls and displays necessary to carry out the task.
.(2) A survey of the control room instruments to be used to fulfill the requirements (1) above. A list of de-ficiencies, if any, will be developed for evaluation.
(3) A walkthrough of the new procedures in the control room or
. control room mockup with licensed operators to verify use-ability and identify deficiencies in either procedure for-mat or control room characteristics.
(4) Evaluation of deficiencies identified to recc: rend satis-l factory solutions to determine significance, to establish priority and to recommend schedule for correction.
These elements will supplement the normal technical review, safety review and operator training that is conducted for all plant procedure
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revisions.
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ge IV.
Use of the 41 ant Computer System-to Correct Human Engineering Deficiencies (NED)
.In the CRDR Summary Report Group 5 of Table V-1 summarized a number of deficiencies for which-the corrective action was displayed via a com-puter driven CRT. Selecting this category for correcting a HED required several criteria to be met: (1) Since the computer is not a safety grade device, it could not be used as the sole display of a parameter to be used in an important to safety task; (2) For all other parameters, the loss of indication via the computer would not result in operator error since backup indication could be made available in enough time to prevent a plant upset; (3) Use of the computer would provide improved information because it was more clearly displayed, integrated with other information or placed in a more convenient positionsin the control room then alternate display devices.
1 Since these criteria minimize the safety significance and importance category of the corrective actions all the deficiencies were placed in a schedule category 3.
Deficiencies 5-1 to 5-4 were given an importance category of B, but since each of these is also being considered;in other corrective action programs or schedule category 2, these corrective actions were give schedule category 3.
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ATTACHMENT 1 Updated table V-1 of Oyster Creek DCRDR Summary Report This attachment updates the table to include comments from Section II of this supplemental report on descriptions of corrective actions and schedule categories.
New schedule categories used in the attached have the following meanings:
Schedule Category 1A Evaluation or study necessary to resolve this item will be completed in 1985.
If study requires a modification to the control room, it will be scheduled at that time.
Schedule Category 18 Modification is scheduled to be installed in 1985-1986 refueling outage.
Schedule Category 3A Evaluation or study'necessary to resolve this item will be completed in time to support installation by schedule category 3.
For reference, categories from previous report have the following meanings:
Schedule Category 1:
Accomplish at the earliest opportunity, but in no
-case beyond the next refueling outage.
Schedule Category 2:
Accomplish by the end of the next refueling outage (1985).
Schedule Category 3:
Accomplish by the end of the 1987 refueling outage.
Schedule Category 4:
Accomplish as convenient, or after the 1987 refueling outage, or, if the need for corrective action is not established, on no definite schedule.
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GROUP 1 FURTHER EVALUATION REQUIRED i
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y Page 1 of 22 ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE.
. RESOLUTION -
CORRECTIVE ACTION CATEGORY
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1-1 Yarway and reactor protection level instruments' ' Evaluate removing density 1A.
are not density compensated causing unnecessary compensation from control level alarms if density-compensated recorder is used instruments.
for control.
1-2 Core region level instruments are not used.
Evaluate making core region Complete instruments operational when pumps are running.
1-3 Need temperature indications for elevations in Upgrade temperature instrumentation.
2, 3 drywell, torus and H & V system.
1-4 Synchroscope operates counter to industry Evaluate making synchroscope rotate 1A
- standard, in standard direction.
1-5 The added facades may aggravate the problem of Measure temperatures if facades are 1A, high temperature in the spaces behind panels.
installed. Correct as necessary.
1-6 The differential pressure instrument currently Evaluate use of present dp meter to 1A provided for the containment spray system display needed information.
measures the difference between she11 side and tubeside pressure and has no functional use.
The emergency procedure calls for a she11 side differential reading, which is only provided locally.
1-7 Displays associated with Rod Worth Minimizer are Consider relocating the electronics.
3 distracting to operator. Rod Worth Minimizer
.(Note that a few of the indicator displays and controls are not.needed on front lights are used and would remain.)
panel.
1-8 Condensate return valve control lacks ability to Operators can work with present on-1A equilibrate heat removed by condenser and decay off control. Evaluate throttle heat from reactor.
control.
1-9 Condensate demineralizers have limited capacity A fluid system modification is 1A
- especially at high powers.
necessary to correct this problem fully. Individual " runout" alarms for feed pumps would help. Evaluate after completion of demineralizer mod now being made.
1-10 Operator is deprived of a rate-of-makeup Evaluate reranging CRD flow meter.
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indication as flow increases.
1-11 Low power feedwater control requires full-time Evaluate a fluid system modification 1A operator attention and results in thermal cycles. (addition of Main Feed Regulator to reactor vessel nozzle.
Block Valves) to correct.
Page 2 of 22 ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION CORRECTIVE ACTION CATEGORY 1-12 Excessive reach required to operate valve to
' Consider automatic control or 1A' control reactor level during startup.
improve location for manual control.
1-13 Need controls for. diesel generator output Analyze, not clear control is IA
- breakers, required.
1-14 Some controls are too sensitive.
Evaluate on a case basis.
1A 1-15 Controls rotate opposite way expected.
Evaluate on a case basis.
1A 1-16 Some variables values are not accurately Treat on a case basis.
IA measured by recorders.
1 2
GROUP 2 RELABELING, DEMARCATING AND OTHER IMPROVEMENTS NOT REQUIRING MODIFICATIONS TO ELECTRICAL CIRCUITS OR FLUID SYSTEM CONFIGURATION (Including Mimicing of Existing Arrangements) o CONTROLS / DISPLAYS o
METER SCALES (Bands, Setpoints, Limits) o RECORDER SCALES o'
LENS CAPS (Colors, Legends) o NORMAL /0FF NORMAL STATUS o
SBM ESCUTCHEONS
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Page 3 of 22 ITEM No.
DEFICIENCY DESCRIPTIDN OF SCHEDULE RESOLUTION CORRECTIVE ACTION CATEGORY 2-1 No warning labels to prevent startup of 2nd Add appropriate labels. (Gl)
I stage (booster) core spray pump before 1st stage pump is on.
2-2 No ready means on either rod display or se-Improved labeling and demarcation; 2
lector mimic to identify the group to which including possible temporary group reach rod has been assigned.
labels should mitigate. (G1) 2-3 The rod display mimic is difficult to corre-Improved labeling and demarcation; 2
late because of the difference in shape from including possible temporary group the rod select mimic.
labels should mitigate. (GI) 3-4 Difficult to determine axes of symmetry; hard Improved labeling and demarcation; 2
to make quick visual check of rod position.
including possible temporary group labels should mitigate. (GI) 2-5 Nomenclature for the locater - labels in the Improve labeling. (GI) 2 rod mimic for the SRM detectors and IRM detec-tors is obscure.
2-0 Indicator Lights for IRMs and APRMs are not Label and demarcate. (GI) 2 clearly tied to specific channels.
3-7 Labeling is not clear for key operated " rod Relabel. (Gl) 2 out permissive" switch.
2-8 Status lights not clearly labeled.
Relabel. (GI) 2 3-9 Turbine steam flow recorder is mislabeled Relabel.
2 2-10 Reheat and extraction steam displays are hard Provide labeling and demarcation.
2 to pick out on panel 7F.
(G1) 2-11 Controls for air ejectors and related equip-Relabel. Rearrangement not 2
ment confusingly arranged.
recommended. (Gl) 3-13 Gland seal displays hard to see among other Relabel. (GI) 2 indicators on 7F.
3-13 Some level meters have confusing scale Provide consistent and improved 2
divisions.
meter scales. (G2) 2-14 Control system water level signal recorder Correct recorder scale. (G2) 2 is calibrated in feet (versus inches for nearby meters).
2-15 Level set points for alann or protective.
Provide appropriate red and green 2
actions are not indicated on level meters bands on level meters, or other set themselves.
point display. (G4)
s Page 4 of 22 ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION CORRECTIVE ACTION CATEGORY 2-16 Core spray system labels lack clarity.
Relabel. (G1) 2 2-17 Status lights for EMRVs not accurately la-Relabel (GI) 2 beled.
2-18 Difficult to correlate electrical displays Provide new labeling and 2
with controls on benchboard.
demarcation.
(G1. G57) 2-19 Some electrical displays and controls are Provide new labeling and 2
mirror-imaged causing confusion, demarcation. (G1, G57) 2-20 Emergency service water controls and dis-Relabel. (G1) 2 plays are confusingly labeled.
2-21 Arrangement and labeling of ventilation system Relabel and consider incorporation 2-Relabel controls is confusing. Mimic would help.
of limited mimic. (GS) 1A-EML 2-23 Because of design modifications, many controls Upgrade jury-rigged recorder and 2
and displays are add-ons (such as recorder and meter scales. (G2) meter scales).
3-23 Controls for radioactive off-gas are obscurely Relabel. (G1) 2 labeled.
3-24 Dilution system controls obscurely labeled Relabel. (GI) 2 2-35 Chemical poison system pressure and flow meters Label. (GI) 2 are unlabeled.
3-26 Chemical poison system indicator lights Relabel. (G1) 2 confusingly labeled.
3-27 Label plates of fire detection system difficult Relabel. (G1) 2 to read and interpret.
3-28 Nomenclature for fire protection system controls Relabel. (GI) 2 inconsistent and confusing.
3-39 No setpoints or limits are formally incorporated Add red and green range bands or 2
i on Oyster Creek displays.
setpoint/ limits label plate. (G4) l 3-30 Displays are rarely labeled with system Relabel. (GI) 2 headings.
l 2-31 Controls used under "off-normal" conditions are Relabel. (G1,'G6) 2 not distinctively labeled.
3-32 Inadvertent actuation of wrong control has Relabel. (G1) 2 occurred.
Page 5 of 22 ITEM No.
DEFICIENCY DESCRIPTION OF' SCHEDULE-RESOLUTION CORRECTIVE ACTION CATEGORY j
2-331 Labels not easy to read - dirt wear letter Relabe'1. (G1) 2 size, etc.
2-34 The identifying component number is not engraved Relabel. '(G1) 2 on most label plates.
2-35 Difficult to coordinate backboard displays with Addition of demorention lines.
2 related benchboard controls.
system overview labels' and better individual labels will correct this deficiency. (G1) 2-36 Displays on panel backboards have horizontal Inconsistency does not appear to 2'
oriented progression, while related controls on create significant operational adjacent benchboard have vertical progression.
difficulties; relabeling and demarcation should alleviate this problem. (G1) 2-37 Some meters have excessively fine scale Correction of display meter scales 2
graduations.
is best handled on a case basis. -(G2 )
3-38 Water level meters and recorder have Correct scale units, use consistent Completed Levels referenced to TAF inconsistent units and zero.
zero for meters and recorder.
2-39 Meters do not have color bands nor limit Add color bands where appropriate.
2 markers.
(G4) 2-40 Several meters and recorders employ odd scale Correct odd scales. (G2) 2 divisions or multipliers.
2-41
" Reheat" and " Intercept" valve positions are Color code label plate and meter 2
displayed on common dual scale meters. The
- pointers, indicators are very confusing and should be color coded.
2-42 Some display scale graduations and unit labels Scale graduations and labels will 2
are too small and difficult to read.
be improved, where meter size 1A permits. Uncorrected meters will be evaluated for replacement.
l (G1. G2) 2-43 There are many instances where operators and Replace meter scales as necessary.
2 technicians have hand-lettered meter scales.
(G2) 3-44 Labels not easy to read; letter size criteria Relabel. (GI) 2 not met.
l 3-45 Display labels are located below display, while When displays are relabeled labels 2
control labels are above controls, should be moved above respective displays. (GI) l l
l
q Page 6 of 22-ITEM No.
DEFICIENCY-DESCRIPTION OF
-SCHEDULE RESOLUTION CORRECTIVE ACTION CATEGORY 2-46 Information on detector which drives the display Provide information on new labels.
2 is seldom provided.
(GI) 2-47 Descriptive labels for individual meters are Relabel. (G1) 2 confusing to read.
2-48 Control room displays do not have limits and Correct as part of general meter 2
setpoints in a clear, unambiguous manner.
upgrading. (G4) 2-4D Yellow color code has various meanings.
All indicators will be reviewed and 1A changed to the color commonly used in the utility industry. (G6) 2-50 ATWOS control display labels are not oriented Reorient. (G1)
Completed.
horizontally.
1 2-51 Recorder scales are often difficult to read.
Provide improved scales. (G2) 2 j
- i 2-52
. Recorders are supplied with temporary dynotape Provide permanent label plates.
2 labels, one of which indicates the file number (GI) of the recording. The purpose of the other number is unknown.
3-53 A number of recorder scales and variables are Replace scales. (G2) 2 hand-lettered.
2-54 On a number of 2-pen recorders on panels 10F and Relabel with color coded plates.
2 12XR, the color code of the recorder pens is not (GI) correlated with the label plate that identifies the variable.
3-55 Glare on benchboard label plates.
Replace label plates with low 2
glare black-on-white plates.
(GI)-
2-53 Pump and valve indicator lights are less than Replace old and discolored lens
- 2. IA 10% brighter than their backgrounds, caps. Evaluate solutions to light
. variability problem.
8 2-57 Some controls have temporary labeling.
Relabel. (GI) 2 3-58 Temporary aids do not look prof essional.
Relabeling program will include 2
the replacement of temporary operational aids. (GI)
Page 7 of 22 ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION CORRECTIVE ACTION CATEGORY 2-59 The alarms which provide the first cue as to a Add unique identifiers for reactor 2
condition requiring entry into the emergency and containment control emergency operating procedure do not have unique operating procedures to alann identifications and/or locations panels, and elsewhere as appropriate.
2-00 labeling of the slarms fcr drywell temperature Relabel alarm title.
2 high is inappropriate.
2-61 The alarm currently labeled " containment spray Relabel.
2 auto start disabled" is mislabeled.
2-62 The 3 indicator lights on the controllers for Relabel. (GI) 2 the 5 electromatic relief valves are labeled misleadingly.
2-63 The containment spray system control currently Relabel. (G1) 2 labeled " dynamic test" is misleadingly labeled.
3-04 It is not clear that the ammeters provided for Relabel. (GI) 2 the containment spray system apply to the emergency service pumps and not to the contain-ment spray pumps.
2-65 It is not clear that the flow-meters provided Relabel. (GI) 2 for the containment spray system are total containment spray flow and not emergency service water flow.
2-66 Drywell vent and purge controls are located on a Relabel and demarcate. Consider 2, I A back panel and arranged in a confusing way with rearranging to provide mimic.
inadequate labeling.
(Gl. GS) 3-07 fontrol switches for valves in cleanup system Relabeling will mitigate; mimicing 2, I A are confusingly arranged.
should be evaluated. (G1) (GS) 2-08 Controls on containment spray systen are mirror-Relateling will reduce chance for 2
- image, error; control operations are deliberate. (G1. GS?)
2-69 The condenser backwash controls are mirror Relabel, evaluate rearrangement 2, IA
- imaged, and/or mimicing. (G1, GS) 2-70 Electrical system displays not well grouped.
Labeling may mitigate. Consider 2, 1 A selected rearrangements. (GI, GS?)
2-71 A mimic would be useful in checking valve lineup Consider rearrangesent or IA (Condenser Backwash Controls).
mimicing. (GS)
Page 8 of 22 ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION CORRECTIVE ACTION CATEGORY 2-72 No universal Color Code for "off-normal" Where "off-normal" status is' 3
condition.
operationally useful, employ yellow '
or amber color. (G6) 2-73 No indication of " normal" lineup of valves and No corrective action recomended 4
other controls for ease of checking.
(problem has been lived with).
2-74 For certain angular positions, the needle of the Consider replacement of meter 4
GE circular electrical meters can obscure the scales. (G2) number adjacent to the scale mark to which it is pointing.
2-75 Differences in units exist between rate and Evaluation will be done to add 1A integral displays for fluid system, labeling showing tank capacities and relationship between volume and level.
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Page 9 of 22'
. ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION CORRECTIVE ACTION CATEGORY 3-1 Single selectable CR0 flow control valve has No hardware change recommended at Complete limited capacity.
this time. Test of CRD system as makeup source is recomunended.
3-2 No procedural guidance or test basis for setting No hardware change recommended at Complete maximum flow from CR0 pumps.
this time. Test of CR0 system as makeup source is reconenended.
3-3 Procedures are not heavily used in many off-Symptom oriented emergency proce-Complete Procedures implemented, normal evolutions.
dures are being developed for DCNGS.
3-4 Need valve controls, suction Dressure and total Run CRD makeup test. Develop plan Complete Test data and design flow indication for CR0 pumps.
of modifications, if shown necessary review resolved.
by the test.
3-5 Walkie-Talkie communications have not been fully Perform test.
Complete Additional battery tested when repeater power has been lost.
powered radios made available for loss of power events.
3s3 Not obvious which of the outputs of the 4 Provide specific instructions.
1 instruments measuring torus water temperature represents the bulk average torus water temperature needed for the containment control procedure.
3-7 Reactor operators appear to misinterpret the Training item.
1
" failure to scram" entry condition to the reactor control procedure.
3 Page 10 of 22 ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION I
CORRECTIVE ACTION CATEGORY 3-8 The conditions for exiting the procedures are Training item i
not explicitly defined and operators think they can exit from a specific second level procedure 1
before they can exit from the procedures as a whol e.
3-9 Simultaneous implementation of the site Consider assigning direction of the Complete Shift Assistants 6 dad Emergency Plan with the emergency operating emergency plan to the director of to each shift.
procedures places an excessive burden on the operations or his designate, who Snift Superintendent.
could be on call.
0 3-10 The scale units and zeros on the newly-added Provide dual scale information I
wide range torus water level indicators are not in procedure (short-term).
consistent with those for the narrow range level 0
indicators. Also, the wide range limits in the Provide dual scalc information 2
procedure are inconsistent with the narrow range on meters and recorders. (G2) limits.
3-11 Appropriate warning regarding the consequences Include appropriate warning in 1
of lining up the core spray system valves needed procedure and training, in the procedure and on the control panel.
Add appropriate warning labels.
2 3-13 Speed / load changer switch works in opposite No action recommended because of Complete Training compensates.
direction expected, risk if changed. Traning allows operators to adapt.
3-13 Present emergency plan format is cumbersome to Provide summary action level matrix.
2 use.
3-14 Control room operators do not carry a pass key Make keys available to operator.
I to control room.
3-15 A third control room operator is desirable.
On many shifts one is provided.
Complete Extra operator will Evaluate providing one on all be made available as shifts.
policy. Not a safety requirement.
3-13 Lack of regular calibration program with some Upgrade calibration program for 2
instruments, nonsafety related equipment.
3-17 Chart paper is not correctly matched to scales Provide better stock of recorder 1
on a number of recorders, paper, appropriately indexed, and readily accessible to control room operators.
3-18 filters were not in place at the fan suction.
Maintain filters in place.
1
Page 11 of 22 ITEM No.
DEFICIENCY-DESCRIPTION OF SCHEDULE RES0tuTION CORRECTIVE ACTION CATEGORY 3-19 Set of operating procedures on desk is worn and ~
Replace procedure' binder and ta'bs.
I dirty.
3-20 It is difficult to establish accurately the Provide appropriate training for Complete existence of power level above 2 percent if the operators to use intermediate range actual power level is the order of 2-5 percent instruments, and the reactor operator uses the Average Power Range Monitor recorders to read power level.
i 3-21 The operator has no instrument by which he can Add appropriate instructions. Add 1, 3 directly read the level reached when flooding instrument, if necessary. (Consider the drywell, use of drywell pressure instrument and wide range torus water level instrument.)
3-22 Emergency operating procedures must be stored in Provide storage space in the control 1
the control room.
room.
3-23 Scrams may result if operator incorrectly Training compensates.
Complete-switches IllM ranges.
3-24 Off gas flow recorder on 10F not used because of Training item.
I lack of experience and knowledge.
3-25 Generator power output meter is ina: curate.
Calibrate "nonsafety" instruments Complete more frequently.
3-26 Changes in plant operating practice are not Revise written procedures to reflect Complete reflected in written procedures.
present plant status and practice.
3-27 Some procedures have not been revised to reflect Revise written procedures to reflect Complete practices shown to be effective.
present plant status and practice.
f' GROUP 4 HARDWARE o.
REMOVAL (Unused, non-functioning) o REARRANGEMENT / RELOCATION (Meters, Switches, etc.)
o
-MODIFICATION (ControlLogic, Interlocks,etc.)
. o REPLACEMENT (Rec' orders, Switch Handles)
'o
-ADDITION (Integrated-Consolidated Display, etc.)_.
o FLUID SYSTEM CHANGE 4
k.
. ~ _ ~...
I.
mt Page 12 of 22 ITEM No.-
DEFICIENCY DESCRIPTION OF.
- SCHEDULE
' RESOLUTION CORRECTIVE ACTION CATEGORY 4-1
-Operator is unable to confirm by meter reading Display output in terms different
'I the " triple-low" water level.
from downcomer water level or' correlate to.Other instruments.
4-2 Meed displays of frequency for diesel generator.
Provide frequency displays.
1' 4-3 Local drywell temperatures that are recorded and Provide specific instruments (as 1
alarmed in the control room are the 5 tempera. :necessary) and instructions on which tures at the five drywell coolers - near the drywell temperature should be used bottom of the drywell.
as.an entry condition.
4-4 There are many differences among the various Provide reference leg temperature 1
reactor water level instruments in terms of the measurements and clear instructions process variables they respond to and their on how to use them to correct sensitivity to the drywell temperature.
reactor water level measurement.
45 LPSM trend recorder is seldom used by operators.
Remove recorder. (G10) 2 4-0 Blank vertical meter on 4F backboard Remove meter. '(G10) 2 distracting.
4-7 Order of instruments is not natural.
Interchange steam flow and condenser 2
vacuum displays.
4-a Steam pressure recorder not easily seen on Provide integrated easily viewed 2
control board.
consolidated display. (Gil) 4-9 Hard to view pressure recorder while using Provide consolidated display. (Gil) 2 turbine bypass controls.
4-10 Lack of reactor coolant temperature information Provide consolidated display. (Gil) 2 on Oyster Creek control board.
Add satuation temperture to CRT.
3 4-11 Direction of motion of turbine control switches
. Modify switches. Consider change 4
work the opposite way expected, when replacing pressure regulator.
4-13 Circular meter pointers move opposite the motion Correct if control switches are 4
of associated control switch, modified.
4-13 Should be a protective cover on vacuum breaker Provide protective collar.
2 control.
~
.4-14 Some controls are not used on generator section Remove unused (or disconnected) 2 of control board.
controls. (G10) 4-15 Quest +cn usern1 ness of wcond MVAR meter.
Remove the " add-on" MVAR meter.
2 (G10)
Page 13 of 22 ITDi No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION CORRECTIVE ACTION
. CATEGORY O-16 unter level indicators are not easily viewed Add consolidated display. (G11) 2 from clean-up system letdown valve controls.
4-17 No display or alarm for reactor building sumps Consider adding appropriate alarms 1A i
or torus room sump in control room.
or displays in control room.
4-18 Reactor water level meters hard to read from Add consolidated display. (G11) 2 IF/2F where core spray controls are located.
4-1g Arrangement of control switches for recirc. pump Modification to valve interlocks and 2
isolation and bypass valves confusing and not control arrangement is planned for same as used elsewhere.
long term.
O-20 A como11cated procedure required to bring Correct anomaly in isolation valve 2
cleanup system on line due to valve control control logic.
logic.
4-21 valve to operate recirculation valve is in high Move valve operation switch to low '
3 radiation zone, radiation location or make system automatic as originally designed.
4-22 No information displayed for vital 480VAC motor Provide improved status information 3
control centers, on vital power.
4-23 Controls and displays for emergency diesel Rearrange (it may be necessary to 2, 3 generators are confusingly arranged.
operate controls under marginal lighting conditions). (G5) 4-24 The raise-lower control for diesel generators Consider rewiring control to make 3
works opposite way expected.
correct.
4-25 Few indications of status of vital low voltage Improved status information on vital 3
(120VAC, 125 VDC) power distribution systems.
power was planned by modification.
Some has been provided by alarm system changes. Provide missing status information.
4-26 Newly added fire protection system controls Rearrange. (G5) 2 haphazardly arranged (pond pump 2 and backup fire pump).
4-27 Status lights for fire system jockey pump still Remove. (G10) 2 remain, though unused.
4-2s Need auto-manual transfer control of condenser Provide transfer function in CR.
3 hotwell control.
4-20 Many instances where displays needed to support Handle on a case basis.
2, 3 operations in off-normal situations are not conveniently located.
R
~
Page.14 of 22-ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION-CORRECTIVE ACTION CATEGORY 4-30 Valve position indicators generally follow a Change lens caps to appropriate 1 2
convention of red for open (flowing) and green color. (Gs) for closed (not flowing). Valve positions displayed on panel 10xF however. use amber for A change to-the intensity of 3'-
the open positions.
the indicator lamp may also be necessary.
4-31 Recorders are unreliable, hard to read, hard to Replacement of some multipoint 2, 3 maintain.
recorders is planned. Evaluate need for trend information on remaining recorders (both multipoint and 2-pen). Provide replacement recorders or other means of displaying trend information (e.g.. Computer trend) where required. (G3, G9) 4-32 Mandle is removed from the spare exciter field Demove this never-used device.
2 thermostat control on panel SF/9F.
(G10) 4-33 Control switch handles should be coded (size, Correct by coding (size, shape, 2
shape, color).
.. color) switch handles.
4-34 Some controls are not adequately identified nor Replacement of switch handles with 2
protected.
redundantly coded handles, e.g.,
shape and color, is reccamended.
4-35 Progression of multiple displays is inconsistent Can usually be corrected by inter-1A with normal conventions (left to right changing the location of a few progression),
displays. (G5)'
4-36 There is some chance of misreading the 2-pen.
Replace. (G3) New recorders should 3
2-scale recorders used throughout the control color code pens with labels, to
- room, facilitate identification of variables.
4-37 Design and operation of strip chart recorders is Replacement of some multipoint 1A inadequate.
recorders is considered. Evaluate need for trend information on remaining recorders (both multipoint and 2-pen). Provide replacement recorders or other means of displaying trend information (e.g.,
computer trend) where required.
(G3, G9) 4-38 Secorders are mechanically unreliable.
Replace recorders.
2, 3 Recorders have been reviewed and prioritized.
Some were replaced in last outage. Others will be replaced in next two outages.
Page 15 of 22-ITEM to.
DEFICIENCY DESCRIPTIDN OF SCHEDULE RESCLUTION CORRECTIVE ACTION CATEGORY 4-39 Selection of time scale and recorder speed often Replacement of some multipoint 1A do not allow the rate of cha ge informatioa the recorders is considered. Evaluate operator needs to be inferred from the recording. need for trend information on remaining recorders (both multipoint and 2-pen). Provide replacement recorders or other means of displaying trend information (e.g.,
computer trend) where required.
(G3, G9) 4-40 Panel components in poor condition.
Refurbish as required.
1B 4-41 High drywell pressure mus'. De confirmed by Locate narrow range drywell pressure 3
consulting a back panel indicator.
indicator on front panel or incorpo-rate in consolidated display. (GII) 4-42 Rate and direction of change of drywell pressure Add wide range drywell pressure re-3 over a wide range must be read from a newly-corder on front panel or incorporate added back panel recorder.
rate of change information in consolidated display or on computer display. (G11. G9) 4-43 All the torus water level instruments utilize Investigate means for ensuring 1A a common standpipe.
standpipe is full.
4-4::
The senior operator and the shift technical Add consolidated display with E0P 2, 3 advisor have difficulty in visually collecting entry variables. (G11) the data they need to execute their overseeing responsibilities.
4-45 Operator must confirm the de-energization of the Indicator lights should be put on IA 8 scram solenoids by checking the 8 indicator front panel.
Itchts on one of the back panels. In addition, burned out indicator light bulbs can lead operator to make a serious error.
4-45 Control of the CRD pumps is lost if power to Being corrected as part of another 2
panel 4F is lost.
modification.
4-47 Water pressure meters do not indicate presence A fluid system modification is 4
or absence of water in water boxes, necessary to ensure that water boxes are full. Remove present meters which are not useful.
4-48 Reactor pressure indicator is redundant to two Consider removing unnecessary 1A heat excha9ger pressure indicators, pressure meter, or make scales consistent, or replace with consolidated display. (Glo)
Page 16 of 22 s
ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION CORRECTIVE ACTION CATEGORY 4-49 Controls for electrically operated relief valves Rearrange. (G5) 2 (EMRVs) are illogically arranged.
4-50 Display for condensate demineralizer dp is Relocate to 5F/6F. (GS) 2 poorly located.
4-51 Distracting extraneous power information is Evaluate need for meters, remove 2
provided for many buses.
unnecessary meters. (G10) 0-52 Veltmeters are above ammeters for A & B Rearrange. (G5) 2 batteries, below for C battery.
4-53 Ground detecting indicator, voltmeters and Rearrange. (G5) 2 anneters inconsistent arraugement.
4-54 Recorder displaying closed cooling water Improve labeling. Recorder modt-Completed temperatures to reactor building machinery and fication, (planned 1983 outage) may turbine building machinery is confusingly enhance readability of these labeled; temperature information is difficult to variables. Long term: consider read; there are no CW alarms.
adding CCW alarms. (G3) 4-55 Excessive reach to valve controls and test Relocate.
2 buttons (too high) on panel 11F.
4-56 Need containment purge and went controls and Evaluated incorporating displays in 2
displays on front panel, integrated display.
4-57 ATWQS reactor recirculation pump trip displays /
Consider relocating.
1A controls are not needed on front panel.
4-58 Two-pen recorders fail as is and the absence of On replacement 2-pen recorders.
IA chart motion may not be immediately obvious, consider use of " power on" light.
(G3) 4-59 Controls difficult to reach, (ATWQS and Steam Consider relocation of steam line 1A line valve controls too high, others too low).
valve controls, for others, no corrective action recommended at this time.
4-60 Vacuum pump controls on panel 13R are opcasite Consider rearrangement, relabeling.
IA the normal lef t-to-right sequence.
(GS, G1) 4-61 Certain valve controls on panel 12XR are out of Consider rearrangement.
IA normal sequence.
relabeling. (GS, G1) 4-62 Control for the 3 feedwater pumps are in a Consider rearrangement, IA horizontal array. while the controls for the 3 relabeling. (GS, GI) condensate pumps that supply them are arranged v!rtically.
Page 17 of 22 ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION CORRECTIVE ACTION CATEGORY 4 ",3 MSIV test Pushbuttons are hard to operate.
Relocation of these pushbuttons (to
-1A a lower location) may improve operability. (GS) 4-64 On panels 13R. left and right, test selection Consider switch replacement.
1A switches for the reheat stop valves and the selectors for the turbine bypass valves rotate throueh 360.
4-65 Inconsistent positioning of " auto" or " normal" No recomunended actions since action 4
of several switches, is deliberate; consequences are minor and do not affect safety.
4-66 The fuel zone reactor level recorder is located Consider providing on consolidated 2, 3 several feet away from other reactor level level display or on computer driven
)
displays.
CRT. (G11 or G9) l l
l^
t.
GROUP 5 COMPUTER SYSTEM ADDITION t
L-.
Page 18 of 22 ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION CORRECTIVE ACTION CATEGORY 5-1 Dispersion of controls and displays causes Provide coordinated displays on 3
difficulty in obtaining coherent picture of plant computer CRT. (G9),
state of torus and drywell variables.
5-2 2-pen recorders do not display trend information Consider use of CRT display for 3A effectively, needed trend. (G3, G9) 5-3 Important variables are displayed gDh on Provide selectable computer driven 3
multipoint recorder, where they are difficult to readouts for operators. (G9) read.
5-4 The recorders used to display the output of Replace the recorders or display 3
individual radiation monitors are unreadable, output on computer driven CRT.
(G3. G9) 5-5 Operator cannot easily determine if change in Provide feedback via Computer Driven Completed flux is that expected for rod movement.
Displays. (G9) 5-G Perturbations in power demand arise that result Provide feedback via Computer Driven Completed in reactivity requirements outside the range Displays. (G9) foreseen in the night orders.
5-7 Reactor engineers may err, calculationally or Provide feedback via Computer Driven Completed typographically, formulating night orders.
Displays. (G9) 5-8 Reactor operator may err. reading night orders Provide feedback via Computer Driven Completed and translating them into action.
Displays. (G9) 5-9 No single reactor power level indication.
Display average neutron power on 3
CRT. (G9) 5-10 Cire water flow, and other variables not Display cire water temperature 3
available on front panels, differential, pump current and steam flow on plant computer CRT. (G9) 5-11 Circulating water inlet temperature not Provide on plant computer 3
displayed on front panel.
CRT display. (G9) 5-12 The automatic control for two valves involved in No short term action recommended on 3
hot well level is outside control room, no control location. Provide valve indication of valve position is displayed in position record on plant computer, control room.
(G9) 5-13 Conductivities displayed on recorders are Display conductivities in plant 3
difficult to read.
computer driven CRT. (G9) 5-14 Voltage information is sparse - especially for Provide Bus Voltage display from 3
the 480 buses, plant computer. (G9)
o fu 7
Page 19'of 22 ITEM No.
-DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION CORRECTIVE ACTION' CATEGORY 5-15 Little temperature information for service Display service water temperature on-3 water.
plant computer CRT. (G9) 5-16 No emergency service water temperatures are Display ESW teaseratures on plant 3
displayed.
computer. CRT. (G9) 5-17 Multi-point recorders for radiation monitors are Operators currently use output 3
unreadable.
meters on panels 1 and 2R.
Provide radiation monitor display on computer CRT. Remove recorders.
(G9) 5-18 Outputs of instrument channels are displayed on Operators currently use output 3
meters outside operator's field of view.
meters on panels 1 and 2R.
Provide radiation monitor display on computer CRT. (G9)
.5-19 Two-pen recorders for radiation monitors are Replace 2-pen recorders or provide 3
unreliable and require frequent maintenance.
needed trend information on computer CRT or by other means. (G9) 5-20 Meed condensate dump and vacuum drag valve
. Consider adding to computer CRT.
3A positions, or flow rates.
5-21 Need closed cooling water system temperature Provide on computer CRT. (G9) 3 displays on front panel.
5-22 Need displays for bearing, winding and water Provide on computer CRT. (G9) 3 temperature for main generator, reactor rectr-culation pump and CR0 on front panel (on demand).
5-23 Meed radiation monitoring readouts on front Provide on computer CRT. (G9) 3 panel (on demand).
5-24 Need turbine information to monitor operation of Provide on computer CRT. (G9) 3 machine on front panel (on demand).
5-25
.Some reactor recirculation pump electrical Remove from front panel, provide on' 3
displays are not needed on front panel.
CRT. (G9. G10) 5-23 Some auxiliary electric power displays Remove from front panel, provide on 3
are not needed on front panel.
CRT. (G9. G10)
GROUP 6 CONTROL ROOM ENVIRONMENT
- o
. REFURBISH PANEL FRONTS (i.e., Painting, etc.)
0._
. LIGHTING
- o VENTILATION o
NOISES 0
ACCESS CONTROL' o
. REARRANGEMENT i
l-t t
i
r z
c, Page 20 of 22 i
ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION CORRECTIVE ACTION CATEGORY.
6-1 Poor workmanship on newly installed fire system Refurbish.
2
/
switches.
6-2 Modifications are not consistent with original Refurbish modifications not 2
arrangement codes, professionally done.
6-3 Room is dusty and floor is gritty.
Clean ducts, maintain filters. If 2
problem persists, provide dust removal in air intake.
6-4 Operators claim high background sound noise Remove continuous air monitor from Completed level.
control room. Consider addition of carpet.
6-5 Poor condition of paint on console benchboard.
Repaint.
1 0-6 Paint on walls has deteriorated.
Repainting of room is planned.
1 0-7 Equipment operators and maintenance technicians A rearrangement of the desks in the 3A somtimes interfere with the operators vision of control area is under consideration, control board.
Relocation of Blocking and Tagging to reduce this problem will be considered.
6-8 tocation of GSS office inhibits an efficient Relocate GSS office to room 4
overview function.
currently occupied by Prime Computer.
0-9 Some controls can be jarred by walking by.
Rearrange traffic pattern by 3
relocation GSS office, Blocking and Tagging desk.
6-10 There is no means for adding or controlling Evaluate installing reliable lA humidity.
humidifier.
0-11 Air conditioning system is unreliable.
Install and maintain filters, clean 3
ducts, maintain records. If records indicate compressors a problem, re-place and upgrade system. Control Room habitability modification will correct.
0-13 Hard to control traffic, noise and confusion in Relocate tagging operator's station.
3A control room.
Relocate shift supervisor's office to control access.
6-13 Present location of GSS/GOS office is unable to Relocate GSS office to room 4
prevent casual entry to control area by currently occupied by Prime personnel who have no reason for being there.
Computer.
A 4
A a.-
A GROUP 7 NO ACTION REQUIRED OR DEFICIENCY CORRECTED f
L h
I i
Y
_, m
Page 21 of 22 ITEM No.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTION CORRECTIVE ACTION CATEGORY 7-1 Core spray valve controls cannot be used to Modify controls.
Corrected throttle flow.
7-2 Interplay of brerier and auto start logic Modify logic.
Corrected complicates the water level control operation on core spray, i
l 7-3 Auto start logic train status incompletely Modify status display.
Corrected l
displayed on alarm panel.
7-4 Effective confirmation of high drywell tempera-Add replacement recorders with Completed ture and high torus temperature requires that selectable digital readouts of replacement recorders be added.
individual data points.
7-5 IRM and LPRM sensitivities are unable to meet Corrected by GPUN Mod " Range 10 Corrected requirements that APRM channels be on scale Addition".
before entering "run" mode.
7-6 Transmissivity of annunciator tiles varies Annunciators are being replaced.
Completed severely.
7-7 The conditional statements imposed on the Reformating of the procedures has Completed operators appeared only once in the original corrected this.
version of the procedures and are not easily remembered.
7-8 The tables of valve lineups and other data Reformating of the procedures has Completed tended to disrupt the information flow of the corrected this, procedures.
7-9 Some operators have difficulty coping with Reformating of the procedures has Completed logical branches (the "If...then" step of a corrected this.
procedure) deciding whether or not to proceed to the next step.
0 7-10 There is some difficulty in allocating responsi-A specific " division of labor" Completed bilities to operators so that they control only system has been worked out.
one key variable at a time.
O Procedures for the key vart-Completed ables have been organized by operator responsibility in color-coded, spiral binders which are stored in a 3-ring binder.
L
1 I
Page 22 of 22 ITEM Co.
DEFICIENCY DESCRIPTION OF SCHEDULE RESOLUTIDN
. CORRECTIVE ACTION CATEGORY 7-11 Inconsistent color used for the position
-Operators have adapted; no action
, displays and positions of air operated scram reconnended.
valves for each rod.
E
>;7-12 Difficult to determine nn what channel output is Corrected by procedural guidance and Completed displayed by pen recorder because of different training.
IBM ranges, j
7-13 Isolation condenser control switch is on 5F/6F Not a serious problem: no l
instead of IF/2F.
corrective action recommended.
7-14 Operators hcve never used controls to control No action required.
the condensate makeup and discharge valves manually.
7-15 Surplus of electrical displays could confuse No evidence of operator confusion.
operators.
(G10) 7-16 Recirculation cleanup flow controller is never No change reconuended.
used in automatic mode.
4
+ 7-17 Controls for turbine and reactor building closed No corrective action necessary.
cooling water pumps and discharge pressure Alarus alert operator to trouble.
displays are out of operator's normal field of view.
7-18 Undisplayed steam line radiation channels could
' Back panel indication is adequate.
}
d 7-19 Service air compressor controls are not needed No action required.
j on front panel.
i l
7-20 Electromagnetic noise problem with some nuclear No corrective action recommended; 4
instruments.
not a safety program.
4 7-21 Neutron flux recorders for IRMs and APRMs have No action recommended. Training ranges difficult to use.
compensates.
}
7-22 Inconsistency among scale units exists with Operators have adapted.
0 O
)
temperature displays (C and F ).
]
7-23 The highest temperatures are founding access-No action at this time. When air ways, but no cross-ventilation provided, conditioning runs, temperatures 0.K.
7 The exhaust opening is much smaller than the No action recommended.
l intake opening causing increased air pressure.
I.
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,-