ML19256G560
| ML19256G560 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/26/1979 |
| From: | Parker W DUKE POWER CO. |
| To: | Baer R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912310460 | |
| Download: ML19256G560 (2) | |
Text
6 DLIKE POWEE COMPANY Powra Dettntwo 422 SocTn Cuencu Stater, CuantorTE. N. C. 2e242 WILLI AM O PA R M E R, J R.
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3?)-4063 December 26, 1979 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Robert L. Baer, Chief Light Water Reactors Branch No. 2 Re: McGuire Nuclear Station Units 1 and 2 Docket Nos. 50-369, 50-370
Dear Mr. Denton:
As a result of the recent NRC staff request as outlined in a November 30, 1979 letter from R. L. Baer to W. O. Parker, we have reviewed the procedures and mechanisms for routing and installing safety-related cables at McGuire. This review revealed no evidence that would indicate basic errors in safety-related cable routing or cable installation. Additionally, these procedures and mechanisms when combined with the quality assurance cable installation checks and our experience to date indica *2 that safety-related cables are installed in accordance with the McGuire separation criteria.
The McGuire separation criteria is outlined in Chapter 8 of the FSAR.
The translation of this criteria into the actual field installation of cables involves several tevels of checks in both design and construction to assure proper routing. Cables at McGuire are routed by computer and are installed per the computer routing cards. Quality assurance personnel closely monitor the installation of safety-related cables to assure that the cables are routed as prescribed on the route card. Additionally, safety-related cables and cable trays are color coded to aid in cable installation and identification.
Previous checks of safety-related equipment and cable separation have been conducted jointly by Duke and the NRC staff during the NRC EICSB site visit (August, 1977) and th? NRC fire protection review and site g > PROG eq W
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Mr. Harold R. Denton Page 2 December 26, 1979 visits (November, 1977, April, 1978, and September, 1978). During the EICSB site visit, redundant NSSS channels of steam generator water level and redundant BOP channels involving the diesel sequencer were traced on drawings and in the field from the appropriate sensors to the final actuated devices and shown to be in accordance with the McGuire separation criteria. Additionally, during the fire protection review and site visits, the independence of electrical equipment ed systems, in particular the residual heat removal pump motors, component cooling water pump motors, and the nuclear service water pump motors and their associated cabling, was reviewed and found to be in accordance with the McGuire separation criteria and the fire protection criteria.
Our review based on the NRC staff's November 30, 1979 letter did, however, reveal one area of design where additional attention is warranted. The area involves routing and separation situations for non safety-related cables routed with safety-related cables. Therefore, bar.ed on our review, Duke Power Company will perform a design review of the routing of all non safety-related cables run with safety-related cables and will take corrective action as necessary to assure conformance with the McGuire separation criteria. This review is scheduled to be completed prior to fuel loading at which time the results of the review and a description of any required corrective action will be provided to the NRC staff.
Very truly yours, i
u
. n.,.
William O. Parker, Jr.
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