ML20247P765
| ML20247P765 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 09/19/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-89709, NUDOCS 8909270268 | |
| Download: ML20247P765 (3) | |
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M Log.# TXX-89709'
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L File # 919 I.
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nlELECTRIC September 19, 1989 W. J. Cahill Earrative Vice President U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington.D.
C.
20555-
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 NRC REQUEST FOR ADDITIONAL INFORMATION -
SAFETY PARAMETER DISPLAY SYSTEM (SPDS)
Gentlemen:
On September-5,1989, the NRC contac'ted TU Electric regarding SPDS open items identified during a recent site audit. Specifically, the NRC requested additional information regarding SPDS availability and SPDS display screen
. readability. Attached are the specific NRC questions and TU Electric responses.
Sincerely,
$Y A
William J.
ehill, Jr.
By:
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RogerD. Walker Manager, Nuclear Licensing VPC/vid Attachment c.- Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) i
.I 8909270268 890919 A
PDR ADDCK 05000445 flp3
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400 North Ohve Street LB 81 Dallas. Texas 75201 l
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. Attachment'to TXX-89709
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. September 19. 1989-I f
Page 1 of_2 L
NRC Question No.'1 a)
Provide a schedule for the completion of the CPSES SPDS availability test as identified in Revision 3 of the SPDS SAR.
i b)
' Provide a schedule to submit a report to the NRC l
upon successful completion of the test.
TU Electric Response:
Using an approved test plan, a thirty (30) day availability test'will be performed within sixty-o (60) days after fuel load.
Sixty (60) days after' the successful completion of this test, a test report shall be made available to the NRC.
NRC Ouestion No. 2 Provide the resolution and schedule for.the following NRC SPDS audit open items.
a)
The overprint of the colored parameter lines in the trend plots caused the hue characteristics to change and thus could result in a loss of meaningful information.
b)
The small numerics end mnemonics on the RVLIS display were difficult to read.
c)
Due to the anti-glare screens, the readability of the messages in the SPDS message area was poor, d)
Discrepancies existed between the SPDS._ keypad and SPDS CRT.
TU Electric Response: a)
' SPDS display maintenance activity has been performed that included the replacement of the CRT, high voltage power supply and yoke assembly. This resulted in a significant enhancement of brightness, resolution, definition and color discrimination of the displays.
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Attachment to TXX-89709 h,.
-September 19, 1989; P
'Page 2 of 2 b)
To.further enhance readability..a design change has been issued to enlarge the mnemonics and numerics on the RVLIS display.
c)~
In conjunction'with Item."a".above,-the effective use of.the anti-glare screens with.no loss of readability has significantly improved the overall picture. quality.
d).
A relettered keypad has been installed to resolve the identified discrepancy.
In addition, a procedure is in piece which identifies an approved list of acronyms and' abbreviations at CPSES.
j-Differences are noted in the SPDS' specification.
Instances where SPDS abbreviations are not consistent with the approved list are recognized in the operator training program during SPDS-operator interfaces.
Closure of the above items will be documented in a human-factors evaluation consistent with the CPSES ongoing program prior to fuel load.for Unit 1.
The Unit 2 SPDS will undergo a similar evaluation prior to Unit 2 fuel
!1oad.
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