ML20063D997
| ML20063D997 | |
| Person / Time | |
|---|---|
| Site: | Summer |
| Issue date: | 07/06/1982 |
| From: | Dixon O SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8207130257 | |
| Download: ML20063D997 (9) | |
Text
{{#Wiki_filter:__ SOUTH CAROLINA ELECTRIC 8c GAS COMPANY poo r os aic a no n vn4 C otuu sa A. Sours C ARoutdA 29218 O. W. Damoe4..J a. Vic e Par neor w e om.. o......o I Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Virgil C. Summer Nuclear Station Docket No. 50/395 Cable Separation
Dear Mr. Denton:
During a visit to the Virgil C. Summer Nuclear Station on June 2, 1982, a member of the NRC Staff expressed concern over the separation of non-safety related cable trays from safety related cable trays as required by Regulatory Guide 1.75, 1974. The design at the Virgil C. Summer Nuclear Station did not meet the spatial distances identified in the Regulatory Guide. However, the design was analyzed and presented in Appendix 8C of the FSAR. Justifica-tion of design by analysis was an option in the Regulatory Guide to meeting the spatial distance requirements. With the Staff's acceptance of our analysis discussed in the Safety Evaluation Report, South Carolina Electric & Gas (SCE&G) considered that the requirements of Regulatory Guide 1.75 were met by analysis. I' After inspecting actual cases in the field, the NRC Reviewer did not think the analysis was adequate and felt that further action should be taken. As a result, SCE&G has identified the i non-safety related trays in the plant that do not meet distance I requirements from a safety related tray and then at some other point in the length of the non-safety related tray, within a fire area the distance requirements are not met between that tray and a safety related tray that is a redundant channel to the first safety related tray. Per telephone conversations with the NRC Staff, if any one of the three trays involved were covered, it was considered acceptable. Spatial violations that are acceptable because one l tray is covered are not listed. The list is attached for your I information. l l 0207130257 920706 ~ l PDR ADOCK 05000395 A PDR
Mr. Harold R. Denton July 6, 1982 Page #2 For the trays identified, SCE&G will, prior to start-up after first refueling, either provide covers or barriers between the non-safety related tray and one of the safety related trays; or will establish a program for testing the protective devices for the
- cables, i.e. circuit breakers or fuses designed to protect the cables from overcurrent, on a sampling basis.
The sampling basis will be such that approximately 10% of the protective devices will be tested every eighteen months. Devices that do not meet the test criteria will be replaced. The test program will be identified as a licensing requirement in the FSAR and documentation will be kept on file at the Virgil C. Summer Nuclear Station. We trust that this program will adequately resolve the Staff's concerns in this area. If_you have any questions please let us know. Ver truly yours, / O. W. ixon, Jr. AW:OWD/fjc cc: V. C. Summer G. H. Fishcher H. N. Cyrus T. C. Nichols, Jr. O. W. Dixon, Jr. M. B. Whitaker, JR. J. P. O'Reilly H. T. Babb D. A. Nau man C. L. Ligon (NSRC) W. A. Williams, Jr. R. B. Clary O. S. Bradham A. R. Koon M. N. Browne G. J. Braddick J. L. Skolds J. B. Knotts, Jr. B. A. Bursey NPCF File
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