ML20148N759

Forwards Supplemental Summary Rept on Dcrdr Showing Increase in Human Engineering Discrepancies as Determined by Addl Operator Surveys,Per Util 880229 Commitment

ML20148N759
Person / Time
Site:	Vogtle
Issue date:	03/31/1988
From:	Gucwa L GEORGIA POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
SL-4427, NUDOCS 8804070322
Download: ML20148N759 (7)

Text

' Georgra Power Company

., . 333 P4dmont Avsnue ev 04 5 6526 <

Malng Address Post O*f ce Box 4545  ;

MFn Geoga 30302

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Georgia Power L.T.Gucwa the scwcrn esearc swem

- Manager Noctear Safety and Licensang SL-4427 0858m X7GJ17-V000 March 31, 1988 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Hashington, D.C. 20555 PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 SUPPLEMENT TO CONTROL R00H DESIGN REVIEH SUPPLEMENTAL

SUMMARY

REPORT Gentlemen:

By letter SL-4181 dated February 29, 1988, Georgia Power Company (GPC) submitted to the NRC a supplemental summary report on the Vogtie Unit I control room design review as required by Operating License NPF-68, License Condition 2.C(7)c. In that letter GPC indicated that additional operator surveys were received after the Detailed Control Room Design Review Report (DCRDR) had been written. Further, we committed that a supplemental report would be submitted to the NRC by April 1, 1988, should results of the additional operator surveys have a significant impact (i.e., more than a 10% increase in Human Engineering  !

Discrepancies (HEDs) noted) on the DCRDR provided. The additional operator surveys have been analyzed and did reveal additional HEDs.

Accordingly, GPC hereby submits a supplemental report which discusses the results of the additional Operator surveys.

Six copies of the enclosed report are p;ovided for your convenience.

4 A copy of the report is being provided to NR; Region II for its review.

Should there be any questions in this regard, please contact this office at any time.

Sincerely, f Y $.h .- lQ L. T. Gucwa JAE/im 00

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U. S. Nuclear Regulatory Commission I March'31, 1988 Page Two ,

Enclosure-l c: Georaia Power Comoany Mr. P. D. Rice '

Mr. G. Bockhold, Jr.

GO-NORMS U. S. Nuc' lear Reaulatory Commission '

Dr. J. N. Grace, Regional Administrator ,

Mr. J. B. Hopkins, Licensing Project Manager, NRR (2 copies)

Mr. J. F. Rogge, Senior Resident Inspector-Operations, Vogtle l

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• GeoigiaPower A ENCLOSURE PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 SUPPLEMENT TO CONTROL ROOM DESIGN REVIEH SUPPLEMENTAL

SUMMARY

REPORT l

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CRDR SUPPLEMENTAL REPORT SURVEY RESULTG This report revises data on previously reported survey P9sults concerning Cumulative offacts of minor Human Engineerino Discrepancies. The previous report is shown. followed by the updated information. The leading number is the Human Engineering Discrepancy numcer for reference to the Detailed Control Room Design Review report.

1222 In the event of a reactor trio, the tile associated with the event illumi-nates. Other tiles illuminate, counter to 0700.

No operator reported a problem with this design feature. No action is planned.

1222 RM Trip First-out -- revised information Ten cercent of operator surveys indicated a problem with this annunciator. Engineering work is in oregress to provide a separate acknowledge / reset control for this annunciator, since some comments concerned the loss of first out data when the other annunciators sharing a control were reset. This change should largely alleviate the problem. Since this annunciator provides the primary operator information on the occurrence of a Safety Injection. In support of the Emergency Operating Procedures, no further action is planned, beyond the individual control.

1282 All annunciators should be recorded on hard copy and where multi input annunciators are used an alam printout sho* 'd identify the individual alarm inputs in the alars condition.

Only 201 felt such a feature would be beneficial. Others cited problems with noise, printer reliability, and review time against such a feature.

Based on a minimal support from operators for such a feature and the complete

• ek of such a feature in the system design, no action is planned.

1282 Annunciator hard copy --

revised infcrmation Thirty-nine percent of the operators felt a hard copy would t ct beneficial. However the problems cited were related to lack Ct reflash capability rather than a hard copy. An engineerinq review has been initiated to determine the technical teasibility of providing a hard copy printout and expanded reflash capabilltv.

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1318 The fo110Eiing parameters, as identified in the ICCR, are not indicated in the control room: 1) RCP seal INJ temp. 2) RCP ACCW thermal barrier flow. 3) CCW flow to RHR HX, 4) Spent fus; pool level, 5) Spent fuel cooling water flow.

No operators reported any problem with this feature. No action is planned.

1018 Spent fuel pool level incicotton --

revtsed information Ten percent of operator surveys indicated a desire for control room indication of spent fuel pool level. However no spent tuel is present and the pool is drained. so the desire is strictiv hypothetical, not based on actual operations. An engineering review has been initiated to determine the technical feasibility of providing a control room display of this level, l

1249 Use of color, colors used on both the proteus and the ERF CRTS to convey information are not consistent in use and meaning with other color codes (Red and Green) in the control room.

Only one operator felt that had ever been a probles, and that had not resulted in a misinterpretation. To further reduce the possibility of confusion the alare state for valves was set as open, so that the red =open= alarm color convention is preserved. No further action is planned on this item.

l 1249 ERF color conventions -- revised information Eighteen percent of operators reported problems, but none reported any actual misinterpetation. The previously reported I change to set the alarm state to match the normal on/off color l

convention should prevent further problems.

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1240 The proteus operating procedure 13504-1 , Rev. O does not describe the overall computer system, and the computer system components with which the operator can interface.

Only one supervisor felt the Proteus procedure was unsatisfactory and that concern dealt with system startup following a computer ' crash' ; a function nonna11y performed by system engineers and technicians, not Control Room Operators. The procedure will be reviewed for potential improvement in this area.

1240 Proteus procedure -- rstvised in ormation Twenty-one percent of operators reported problems with the Proteus computer operating procedure. The problems stem from the brief treatment of normal operations in the procedure. and the relatively difficult operator interface software. The procedure will be revised to address these problems.

1244 System status feedback, the proteus does not provide feedback to the j operator as to computer system status (i.e. run, stop, failed, on line).

Half the -survey indicated a problem with this. The Proteus fails with the current display; data is not updated and the clock on screen stops changing. The failure is not obvious until the clock error is noticed or some operator input is attempted. By contrast the ERF computer screen blanks out after a 15 second interruption of computer data. An Engineering review has been initiated to develop a cosiputer failure indication.

1244 Froteus computer status -- revised infccmatter Sinty-four percent of occerators reported problems with the lack of computer status information. As previously reported, an engineering review has been initiated to develop a ccmputer tallure indication.

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1270 Provisio3s are not included to provide upon operator request, printouts by alarm group (eg. SYSTEM, SUS $YSTEM. COMPONENT).

While 265 of operators felt this would be beneficial, hardware limitations on changes preclude significant improvement. See HED 1267 for more infor-mation. N) immediate action is planned.

1279 Proteus alarm groupta -- rovtsed information Half the operators felt this would be beneficial. However the system does have this capability. The deficency in the operating procedure. In conjunction with the relatively ' unfriendly' software has prevented effective use of its features. The procedure revision ( HED 1240 ) will help resolve this problem.

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