ML20247M135

Provides Supplemental Info to Satisfy 890112 Commitment Re Dcrdrs & SPDS.Station-specific Set Point Change to Minimize Deflections for Narrow Range Containment Floor Sump Level Will Be Implemented by 890901.Supporting Info Encl

ML20247M135
Person / Time
Site:	Byron, Braidwood, 05000000
Issue date:	06/30/1989
From:	Chrzanowski R COMMONWEALTH EDISON CO.
To:	Murley T Office of Nuclear Reactor Regulation
References
RTR-NUREG-1002 0217T, 217T, NUDOCS 8908010454
Download: ML20247M135 (7)

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Edison 72 West Adams Street. Chicago, Illinois

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%. Clucago, Ilknois 60690 - 0767 June 30, 1989 I

i Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation ,

U. S. Nuclear Regulatory Commission j Washington, DC 20555 l

Subject:

Byron Station Units 1 and 2 Braidwood Station Unit 1 and 2 l DCRDR Implementation RFC Docket Nos. 50-454/455 and 50-456/457 References (a) January 12, 1989, letter from R. A. Chrzanowski to T. E. Murley

Dear Dr. Murley:

Reference (a) contained several Byron and Braidwood DCRDRs and SPDS commitments. This letter provides the supplemental information to satisfy those commitments.

Byron Station received permission to extend four HEDs f rom the first outage implementation schedule for both units. The following solutions and implementation schedules are proposed.

11EP__120.1 This HED is concerned with mounting 005 cards and Caution cards from the handles of " thumb control switches". Commonwealth Edison Nuclear Engineering Department designed a device that will be used at Byron and Braidwood Stations as well as in the Braidwood simulator. A picture of the device is contained i in Attachment A. The device is presently in the manufacturing process. The 250 switcher per unit and the 70 at the remote shutdown panel will be installed by the completion of the next refueling outage for each Byron Unit.

Installation will begin after the receipt of the devices for switches that can be taken out-of-service while the units are at power.

BED B442 This item required a method for the main evntrol room public-address (PA) system to override the other PA systems. A test solution was developed that will add components to each PA station. This solution worked well and at the present time the vendor is making the additional components. Since this colution will be used at the Quad Cities and Dresden Stations as well as at Byron and Braidwood, the vendor is not able to supply all the ccmponents at the same time. Therefore, the Byron components are scheduled for delivery in 9908010434 890630 dgef PDR ADOCK 050004S4 fl P PDC il .

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, time to be; installed during the Byron Unit 1 refueling outage. There are l several PA stations that can only be accessed during an outage on Unit 2. j l

These station will, therefore, be modified during the next Unit 2 outage.

1[EDs 8253 and 1459 This item detailed the problem regarding the lack of lamp test capability and the excessive light bulb replacement rate. The proposed solution to the problem requires the replacement of the existing incandescent bulbs with LEDs. The Commonwealth Edison Nuclear Engineering department has been working with various lighting vendors to obtain a suitable replacement for the light I bulbs. Many samples of Light Emitting Diodes have been received and checked in a 'est module for proper illumination. To date, the red LED comes closest to mee&ing the Human Factors illumination requirements. However, using this particular LED, a resistor replacement is required in each light module. This would seguire intensive manpower requirements and an equally long time period for installation. At this time, Nuclear Engineering is working with an LED manufactusv to create an LED to specifically meet the electrical requirements, heat generation restrictions, fire code adherence, and seismic qualification ,

for the application at the Byron and Braidwood Stations. The final design is  !

expected to be developed by November 1, 1989, with implementation at Byron Station by the end of the next refuelirg outage for each unit. Commonwealth Edison will provide an update on the progress by November 1, 1989.

Reference (a) also discussed the submittal of a revised color use matrix.

After a reevaluation by the Commonwealth Human Factors Group and the Stations of the control rooms at Byron and Braidwood, the use of the color Orange could not be found. Therefore, Attachment A contains the revised page 8 of the Commonwealth Edison response to NUREG-1002 Supplement 4, Section 18, titled Byron /Braidwood Color Use Matrix.

Finally, reference (a) discussed two SPDS leonic spokes that showed appreciable deflection. Byron and Braidwood Stations decided that a station specific set point change is needed to minimize the deflections for the narrow rance containment floor sump level and the wide range steam generator level.

These setpoint changes will be fully implemented by September 1, 1989.

If any further questions arise, please direct them to this office.

Very truly yours,

/ W R. A Chrzanowski t NucleP) (icensing Administrator cc: Byron Resident Inspector Eraidwood Resident Inspector L. N. Olshan - NRR S. Sands - NRR Region III Office 0217T 1-2

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BYRON /BRAIDWOOD COLOR USE MATRIX j COLOR CODE LOCATION u l i

YELLOW Caution-Zone Band MCB Highlights-Lettering PROD and Static Objects Iconic SPDS RED / GREEN Intermediate Valve MCB Positions BLACK Return from Alarm SER PRINTER Channel Numbers RM-11

• Location at both Byron and Bruidwood, unless otherwise i specified.

The Byron /Braidwood main control boards use green board color coding conventions whereas the CECO computer display conventions currently do not use green boaro coding. The feasibility of using green board coding for the computer graphics has been explored at both Byron and Braidwood. At Byron, the plant status, pressurizer, and reactor coolant graphic displays have been modified to the green board coding  ;

cons 1 stent with the main control board. However, the green. board '

coding does not provide for indication of equipment status beyond normal / abnormal.

The CECO computer display conventions will be modified to green board conventions for Byron and Braidwood and these conventions will be implemented on the graphic displays.

The use of shape coding to provide equipment status information in adddtion to color coding will also be explored.

IMPLEMENTATION By the completion of the Second Refueling Outage.

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