ML20235F101
| ML20235F101 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 06/23/1987 |
| From: | Hunsader S COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| References | |
| 3238K, NUDOCS 8707130215 | |
| Download: ML20235F101 (2) | |
Text
{{#Wiki_filter:. [rw. j l ) C:mm:nwrith Edison - One First National Plaza Chicago, Ilhnois l [ Chicago, litnois 60690 - 0767 \\ - 3 dress ReTyWPo5i~Offic'e FoT76F V/ i June 23, 1987 l Mr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission l l Washington, DC 20555
Subject:
Braidwood Station Units 1 and 2 Detailed Control Room Design Review (DCRDR) Safety Parameter Display System (SPDS) l NRC Docket Nos. 50-456 and 50-457 l Reference (a): October 24, 1986 SC Hunsader letter to H. R. Denton (b): March 2, 1987 JA Stevens memorandum to SA Varga j
Dear Mr. Murley:
l Reference (a) provide Commonwealth Edison's committment to add a title to the iconic displays to more clearly indicete the wide range and the narrow range, as applicable. At this time this work has been completed for l Braidwood Stations Units 1 and 2. l Reference (b) provided notification of the DCRDR and SPDS site I audit for the Byron and Braidwood Stations for March 10 and 11, 1987, and provided a listing of Human Engineering Deficiencies (HED's) that required action. During the audit, all but a few of these HED's were resolved. During a conference call held on June 23, 1987 with members of your staff the following DCRDR items were presented as requiring action: 1. The evaluation of the long term engineering solution to the problem of radio transmitters that can inadvertently activate safeguard systems. 2. The engineering evaluation addressing the lack of lamp test capability. 3. The long term engineering solution to the indicator light bulb burn-out problem. 4. The documentation of the detailed color vs. use metrix for the control room color coding and a committment to make color coding in all of the control room context consistent with " green board" concept. 8707130215 B70623 hCoJ PDR ADOCK 05000456 F PDR O i
-g-l l S. Documenting a clarification of the license response to HED #0165 i regarding computer printer speed in order to provide assurance that data will not be lost during a major event. Also, during that conference call the following SPDS items were l presented as requiring action: l. Wide Range Iconic Display - 4 of 8 parameters varied from desired values enough to detract from the SPDS display: a. Reactor Vessel level indication system (RVLS) was reading properly but values spiked periodically. b. High radiation level remained at alarm set-point. c. Wide range Steam Generator level was reading far enough from set-point to be distracting. d. Containment pressure was indicating far enough from set-point to skew the iconic display 2. Narrow Range Iconic Display - 3 readings were off the set-point: l a. High radiation alarm b. Containment temperature c. Narrow range Steam Generator level. Based upon our understanding of these items, Commonwealth Edison will provide a proposed resolution to these items by Augutc 31, 1987. l Please address any questions concerning the matter to this office. l Very truly yours, -{ = : :,& S. C. Hunsader Nuclear Licensing Administrator bs l cc: J. Stevens i UW Resident Inspector l 3238K - _ - _ _ _ _ _ _ _ _}}