ML20079J278

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Interim Deficiency Rept Re Design of Robertshaw Controls Co Thermostatic Valves Installed in Colt Industries Diesel Generators.Initially Reported on 820602.Procedure to Inspect & Modify Valves Being Developed.Also Reported Per Part 21
ML20079J278
Person / Time
Site: Marble Hill
Issue date: 12/17/1982
From: Shields S
PSI ENERGY, INC. A/K/A PUBLIC SERVICE CO. OF INDIANA
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
REF-PT21-82 10CFR-050.55E, 10CFR-50.55E, SVP-0061-82, SVP-61-82, NUDOCS 8212280157
Download: ML20079J278 (2)


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PUBLIC SERVICE INDIANA S. W. Shields December 17, 1982 senior vice President -

S82-13 Nuclear Division SVP-0061-82 Mr. James G. Keppler, Docket Nos.: STN 50-546 Regional Administrator STN 50-547 U. S. Nuclear Regulatory Commission Construction Permit Nos.:

Region III CPPR - 170 799 Roosevelt Road CPPR - 171 Glen Ellyn, Illinois 60137 Marble Hill Nuclear Generating Station - Units 1 and 2

Dear Mr. Keppler:

On June 2, 1982, Mr. R. H. Porter of Public Service Company of Indiana, Inc. (PSI) notified your office of a potentially reportable item as required by 10 CFR 50.55(e). Colt Industries issued a report under 10 CFR 21 which identified certain thermostatic valves with a potential failure mode which might cause overcooling of their emergency diesel generators.

The failure mode of the thermostatic valve is a loose nut which allows an extended stroke of the valve. This additional stroke causes the thermal assembly to control at a lower temperature thus overcooling the diesel engine. After this problem was discovered the valve manufacturer, Robertshaw Controls Company, revised their valve design to require soldering of the subject nut to its belt. However, Robertshaw Controls has been unable to determine which nuclear stations may have received the earlier, unsoldered design. Colt Industries is presently working with Robertshaw Controls to develop a procedure to inspect, and where required, modify the valve assemblies. This procedure will be used first to inspect operating units and inspections will be scheduled for non-operating units at a future date.

This letter is intended to fulfill the requirements of an interim report as defined in 10 CFR 50.55(e). A further report will be filed on or before April 15, 1983.

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DEC 2 0 1982 P. O. Box 190, ' Jew Washington, Indiana 47162 812. 289.3000

PUBUC SERVICE Letter:

J. G. Keppler December 17, 1982 S82-13 SVP-0061-82 If you have any questions regarding this matter, please contact me at your convenience.

Sine rely,

. W. Shields SWS/LGY/bak cc: Director of Inspection & Enforcement U. S. Nuclear Regulatory Cornission Washington, D. C.

20555 J. E. Konklin J. J. Harrison