ML20151M593

Forwards Revised Page 22 to Supplemental Summary Rept on Control Room Design Review.Page 22a Also Encl

ML20151M593
Person / Time
Site:	Vogtle
Issue date:	07/27/1988
From:	Hairston W GEORGIA POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
VL-4, NUDOCS 8808050251
Download: ML20151M593 (4)

Text

. . . , 4 r- ,- 1 Cwrgia Power Corroany 313 Pedmont Avenue

, . ,

• Atlanta, Ge0rgia 30308

. Telephone 404 526 6526 MaAng Address.

Post OfEce Dor 4545 Ananta, Georgia 30302 Georgia Power nuci..r op.r uon. o.a.rtr,,.ni ,,m, un mr.c ya VL-4 1035m X7GJ17-V000 July 27,1988 U. 'S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 PLANT V0GTLE - UNIT 1 ,

NRC DOCKET 50-424 OPERATING LICENSE ?PF-68 CORRIGENDA TO SUPPLEfENTAL SUMMRY REPORT ON CONTROL ROOM DESIGN REVIEW Gentlemen:

By letter SL-4181 dated February 29, 1988, Georgia Power Company submitted a supplemental summary report on the Vogtle Unit I control room design review. Information concerning the Safety Parameter Display System (SPDS) was also included in the aforementioned report.

It has been brought to our attention that page 22 of the supplemental summary report contained an incomplete sentence in the discussion on the SP OS. Enclosed are revised pages which supercede the original page 22.

The change to the enclosed page 22 is denoted by a bar in the margin.

Because of the length of the corrected sentence, it was necessary to complete the text of the affected report section on an additional page, page 22a, which is enclosed. We regret any inconvenience that the incomplete sentence may have caused in your review of the report. -

Should you have any questions in this regard, please contact this office at any time.

Sincerely, ht)..b. h W S W. G. Hairston, III Senior Vice President, '

Nuclear Operations JAE/Im

Enclosures:

Corrected report pages 22 and 22a c: (see next page) .

O h '

l 8808050251 880727 PDR ADOCK 05000424 P PDC ,

Georgia PowerAn U. S. Nuclear Regulatory Comission July 27, 1988 Page Two c: Georgia Power Company Mr. P. D. Rice Mr. G. Bockhold, Jr.

GO-NORMS U. S. Nuclear Regulatory Comission Dr. J. N. Grace, Regional Administrator Mr. J. B. Hopkins, Licensing Project Manager, NRR (2 copies)

Mr. J. F. Rogge, Senior Resident inspector-0perations, Vogtle 1

1035m

?%??s

VIII. Safety Parameter Display System A. fiRC Audit The NRC audit of the Vogtle Safety Parameter Display System

,(SPDS) found that it incorporated accepted Human Factors Engineering principles. However, the flRC consultants' Technical Evaluation Report (TER) suggested a number of areas for potential improvements.

Operator input on those items was collected in conjunction with the Operator Survey (Appendix 2). A discussion of survey results and disposition of each item follows.

B. Suggasted Design Improvements

1. In the SPDS color-coding scheme, perceptual cues for challenges to CSFS are lost when a CSF parameter is of questionable validity. Some other cue should be provided to indicate questionable data.

l l DISPOSITION - The use of a purple Critical Safety Function l

Status Tree (CSFST) status, when the computer data is bad, is intended to alert the operator that the computer can no longer evaluate the status of that function. The Plant Operator is then required to monitor the CSFST using Operations Procedure 19200 dCritical Safety Function Status l

Trees" and control panel instruments. The software for determination of ' bad' status of the CSFST inputs has been changed to consider a parameter l

' good' as long as two iaputs agree in value (previous sof tware considered a parameter value ' bad' if 1 of 3 or 1 of 4 channels deviated from the others).

22 a

i ,

^K This change and the backup procedures' support operator monitoring of the CSFST. Operator Survey responses shcwed no problems with use of the SPDS for monitoring the CSFST in support of the Emergency Procedures; however, 35% expressed problems with the radiation function overview.

d l

l 22a

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