ML20070U943

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Final Deficiency Rept Re Corrosion of Transamerica Delaval Diesel Generator Control Panel.Initially Reported on 810320. Replacement Voltage Regulation Panel Will Be Reinstalled by 830817 & Procedure BNP-QCP-1.3 Initiated
ML20070U943
Person / Time
Site: Bellefonte Tennessee Valley Authority icon.png
Issue date: 02/03/1983
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
10CFR-050.55E, 10CFR-50.55E, NCR-1380, NUDOCS 8302140094
Download: ML20070U943 (2)


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TENNESSEE VALLEY AUTHORITY CH ATTANOOG A. TENNESSEE 374ot 400 Chestnut Street Tower II February 3, 1983 BLRD-50-439/81-28 o

U.S. Nuclear Regulatory Commission a

Region II Attn:

Mr. James P. O'Reilly, Regional Administrator l'.

<~s 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

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Dear Mr. O'Reilly:

BELLEFONTE NUCLEAR PLANT UNIT 2 - CORROSION OF DIESEL GENERATOR CONTROL PANEL - BLRD-50-439/81 FINAL REPORT The subject deficiency was initially reported to NRC-0IE Inspector J. Crlenjak on March 20, 1981, in accordance with 10 CFR 50.55(e) as NCR 1380. This was followed by our interim reports dated April 20, June 25, October 2, and December 18, 1981 and September 20, 1982.

Enclosed is our final report.

If you have any questions concerning this matter, please get in touch with R. H. Shell at FTS 858-2688.

Very truly yours, TENNESSEE VALLEY AUTHORITY DS W h L. M. Mills, Manager I

Nuclear Licensing Enclosure l

cc: Mr. Richard C. DeYoung, Director (Enclosure) l Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

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.. TB A7 An Equal Opportunity Ernployer

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ENCLOSURE BELLEFONTE NUCLEAR PLANT UNIT 2 CORROSION OF DIESEL GENERATOR CONTROL PANEL NCR 1380 BLRD-50-439/81-28 10 CPR 50.55(e)

FINAL REPORT

-Description of Deficiency One of the Bellefonte diesel generator's vontrol panels was improperly stored onsite by TVA. As a result, the ferrous metal parts of the subcomponent voltage regulation panel have oxidized to the extent that the component is not capable of performing the function for which it was intended. The Laproper storage occurred after the panels were transferred 4

to their permanent installed locations in the diesel generator building.

All panels were essentially stored identically, however, proper upkeep of j

protective coverings for the panel was not maik.lained. Inspection of the three other panels indicated no existence of corrosion or oxidation. The existence of the oxidation was discovered during performance of checkouts by the electrical engineering unit. In addition, corrosion of other components in the control panel (plates, nuts, bolts, etc.) have rendered the panel inoperable in its present condition.

Safety Implications The rusted components of the diesel generator control panel represent significant damage to that piece of equipment. The voltage regulation panel is so thoroughly corroded that it will. not function in its present condition. Failure of the voltage regulator consequently results in an inability to properly control the output of the generator. In its uncorrected condition, the diesel generator could not perform its intended i

safety function. This condition could adversely affect the safety of l

operations of the plant.

Corrective Action The vendor (Transamerica Delaval) has notified TVA that the diesel generator's damaged voltage regulation panel, a component of control panel 2RT-ELCP-2-B, is beyond repair and must be replaced. TVA has received a replacement panel and is awaiting instructions regarding reinstallation requirements of components'in the panel. All~ work will be completed by August 17, 1983

.Regarding reoccurrence control for this nonconforming condition, procedure BNP-QCP-1 3 was initiated on November 7, 1980, to provide greater emphasis on maintenance of equipment after installation in the permanent location.

This procedure was implemented as part of the resolution of BLN QA audit deficiency BN-M-80-05 as outlined in TVA's final report (reference letter from L. M. Mills to J. P. O'Reilly dated July 31, 1980). These actions were reviewed by the NRC and the 50.55(e) item closed in inspection report 50-438/81-12 and 50-439/82-12.

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