ML20081G689
| ML20081G689 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/20/1983 |
| From: | Tucker H DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-SSINS-6820 IEB-83-03, IEB-83-3, NUDOCS 8311070152 | |
| Download: ML20081G689 (2) | |
Text
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I e-3 DUKE POWER GOMPANY USNPC R" -; iN :j P.O. HOx 33180 A7
. /; p. i A CHAMLOTTE, N.o. 28242 HAL11. TUCKER TELEF TONE vs.a emessomir, (704) 373-4531 October 20, 1983 33 mM P3 47
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.n Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303
Subject:
Oconee Nuclear Station Docket Nos. 50-269, -270, -287
Dear Sir:
As specified in IE Bulletin 83-03 dated March 10, 1983, concerning check valve failures used in diesel generator water cooling systems, please find attached a report providing our response to Action Item 5 for Oconee Nucle.ar Station.
My letter of June 20, 1983 provided a report in response to Action Item 4.
As stated in the June 20 submittal, the only on-site diesel generator at Oconee is associated with the standby shutdown facility and, thus, the only check valve of concern is valve number CCW-284.
I declare under penalty of perjury that the statements set forth herein are true and correct to the best of my knowledge, executed on October 20, 1983.
Very truly yours,
~
Hal B. Tucker PFG/php Attachment cc: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. J. C. Bryant NRC Resident Inspector Oconee Nuclear Station Mr. John F. Suermann Office of Nuclear Reactor Regulation
-U. S. Nuclear Regulatory Commission
[g Washington, D. C. 20555 y
g 8311070152 831020 PDR ADOCK 05000269 G
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JP0/HBT/PFG October 20, 1983 Duke Power Company Oconee Nuclear Station Response to IE Bulletin 83-03 Action Item 5 Licensees are requested to submit a report to the NRC within 90 days of completion of the results of the initial valve integrity verification procedure performed in accordance with (3) above.
For those valves which i
are found to have undergone either partial or complete disassembly of valve internals, a description of the failure mode should be included.
Response
The initial valve integrity verification for CCW-284 consisted of a forward 4
flow test which was completed on May 25, 1983 and a backflow test which was completed on September 17, 1983. The procedures used are described in the response to Item 4 of the June 20, 1983 submittal.
For the forward flow test, a flow rate of 600 gpm was obtained through the valve. A flow rate i
of 0 gpm was observed during the backflow test.
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