ML20070J663
| ML20070J663 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/20/1994 |
| From: | Shelton D CENTERIOR ENERGY |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 2232, IEB-88-004, IEB-88-4, NUDOCS 9407250256 | |
| Download: ML20070J663 (2) | |
Text
e CENTERIOR ENERGY 0200 Om kee Bouievo'd W A M P55 Donoid C. Sutton incependence OH PO Bon 946G Senior Wce President 216 447 3t00 C'eveford OH 4410t 460 Nuclear Docket Number 50-346 License Number NPF-3 Serial Number 2232 July 20, 1994
\\
United States Nuclear Regulatory Commission Document Control Desk Washington, D.
C.
20555
Subject:
Status of Issues Related to NRC Bulletin No. 88-04:
Potential Safety-Related Pump Loss Gentlemen:
The purpose of this letter is to inform the Nuclear Regulatory j
Commission (NRC) of the status of a procedure change related to NRC Bulletin No. 88-04, entitled " Potential Safety-Related Pump Loss" (Log No. 1-1803).
On June 6, 1994, Mr. Garmon West, NPC Project Manager for the Davis-Besse Nuclear Power Station (DENPS) Unit Number 1, requested that Toledo Edison provide the status of the procedure change discussed j
in the original response to this bulletin.
Toledo Edison's letter Serial Number 1-823, dated September 8, 1988 provided the initial response to this bulletin.
In this letter, Toledo Edison committed to revise the Component Cooling Water (CCW) System operating and alarm procedure. A temporary procedure revision was completed prior to the end of the fifth refueling outage and a final revision became effective on June 9, 1990, to system procedure DB-OP-06262, entitled " Component Cooling Water System Procedure".
This procedure was revised to include a minimum continuous flow requirement for the CCW pump at 3000 gpm.
In addition, the procedure specifies that the CCW pumps are not to be operated at less than 3000 gpm for more than four hours per 30 days.
Toledo Edison considers this item addressed in its response to NRC Sulletin No. 88-04 as complete.
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License Number NPF-3 Serial Number 2232
,Page 2 Should you have any questions or require additional information, please contact Mr. William T.
O'Connor, Manager - Regulatory Affairs, at (419) 249-2366.
Very truly yours, Q
ff KA /1,j cc:
J.
B.
Martin, Regional Administrator, NRC Region III S.
Stasek, DB I NRC Senior Resident Inspector R. J.
- Stransky, Jr., DB-1 NRC/NRR Project Manager Utility Radiological Safety Board
.