ML20101M326
| ML20101M326 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/29/1992 |
| From: | Mccarthy D CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NLS-92-185, NUDOCS 9207080178 | |
| Download: ML20101M326 (2) | |
Text
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CNLL Carolina Power & Light Company JUN 291992 SERIAL: NLS 92 185 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS, 1 AND 2 DOCKET NOS, 50-325 AND 50-324/ LICENSE NOS. DPR-71 AND DPR-62 RESPONSE TO ALLEGATION NO. RII-92-A-0093 Centlemen:
By letters dated May 5, 1992 and May 7, 1992, the NRC transmitted to Carolina Power 6 Light Company (CP&L) details relative to Allegation No, RII-92.A-0093.
The purpose of this letter is to provide the CP&L response to the identified Concerns.
The findings of our investigation are summarized in this letter.
Specifics relative to each issue noted in the NRC letters have been shared with members of your staff. In addition, walkdowns of arecs in question have been performed both independently by CP&L and with members of your staff.
That portion of the concern involving an incorrectly sized structural beam installed between 50' and 80' elevations in the Reactor Building could not be substantiated; however, similar beams in a different location in the Reactor Building had been self-identified, and permanent fixes completed on the beams in 1991.
The concern that shiny tags (bands) have been placed on conduit supports to denote whether a seismic analysis has been completed for that support could not be substantiated. The tags placed on conduit supports, as referenced in the concern, are identification tags, and are required by the existing conduit support work procedure (WP-215), The work procedure requires that the conduit support identification number and the conduit support classification be denoted, preferably on the same band.
With regard to the generic issue of conduit support deficiencies in the.20' elevation of the Reactor Building, conduit support-related deficiencies have been found in both Reactor Buildings. The deficiencies were found during the extensive plant equipment condition walkdowns that have been performed since early April 1992, other elevations of the Reactor Building have also been inspected during the plant walkdowns. The findings of this effort have been shared with members of your staff.
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Document Control Desk NLSo92-185 / Page Control Room inspections and reviews of the modifications referenced in the May 7, 1992 letter did not substantiate the concern of a missing bolt on a Control Room conduit support above a panel; however, one bolt was found missing from a conduit support located in the Control Room area during a walkdown with a member of your staff.
In addition, plant equipment condition walkdowns, similar to those performed in the Reactor Building, were also conducted for the Control Room.
Nonconforming equipment conditions found during these and other walkdowns are being added to and dispositioned under i
the Brunswick corrective action program.
CP&L believes that reasonable effort has been made to investigate the above allegations (including field walkdowns with members of your staff), and that appropriate corrective actions have been taken. CP&L considers this matter closed unless information is received warranting additional investigation.
Please refer any questions regarding this submittal to me at (919) 546-6901.
Yours very truly,
- ~ ;/
David C. McCarthy f/
Manager Nuclear Licensing Section i
KAH/jbw cc:
Mr. S. D. Ebneter Mr. R. H. Lo Mr. R. L. Prevatte i
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