ML20137S103
ML20137S103 | |
Person / Time | |
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Site: | Hope Creek |
Issue date: | 11/06/1985 |
From: | Martin T Public Service Enterprise Group |
To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
References | |
REF-PT21-86-052-000 PT21-86-052-000, PT21-86-52, NUDOCS 8512060159 | |
Download: ML20137S103 (2) | |
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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217M0211999-09-20020 September 1999
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Nuclear Business Unit Salem,Hope Creek Emergency Preparedness, 980303 1999-09-08 |
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Thomes J. Martin Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/430-8316 Vice President Engineering and Construction November 6, 1985 Dr. Thomas E. Murley, Administrator U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Dr. Murley:
SIGNIFICANT CONSTRUCTION DEFICIENCY HEAT BUILD-UP IN EDG CABINETS HOPE CREEK GENERATING STATION On April 3, 1985, a verbal report was made to Region I, Office of Inspection and Enforcement representative, Mr. E.
Kelly, advising of a significant construction deficiency concerning heat build-up inside the Generator Control Cabinets.
On May 6, August 7, and September 13, 1985, interim reports were sent to your office. In conjunction with our September 13, 1985, letter, the following information is provided as our final
-report in accordance with 10CFR50.55(e).
Design Change Packages (DCP's) 570 and 7079 have been implemented on the Hope Creek Diesel Generators with the exception of one (1) replacement current transformer (CT) which was damaged during shipment. These DCP's provide for, respectively, replacement of the center CT's and increased and redirected airflow within the control panels.
On October 30, 1985, the CT core temperatures in the B generator potential and excitation control panels were monitored and .
recorded during 13 continuous hours of operation. The loading on the generator was, approximately, 4400 KW, 700 amperes and 60 hertz. +
8512060159 85110g PDR ADOCK 05000 p S
ff0 st of;
o Dr. T. E. Murley 2 11/6/85 The temperatures were monitored and recorded utilizing a Molytek Chart Recorder, model #27025 (M&TE #HC-IC-T002) which was programmed to record the temperatures at 5 minute intervals. The core temper-atures appeared to stabilize after 8.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of equipment operation.
The highest core temperature recorded during the next 4.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> was 78.2 C which is well below the 100 C threshhold provided by the vendor.
Very truly y'ours,
,(jh '
C Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, D. C. 20555 '
NRC Resident Inspector - Hope Creek P. O. Box 241 -
Hancocks Bridge, NJ 08038 Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GA 30339
. ~