ML19253C198
| ML19253C198 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 11/16/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Mary Johnson SOUTH CAROLINA ELECTRIC & GAS CO. |
| References | |
| NUDOCS 7911300141 | |
| Download: ML19253C198 (2) | |
Text
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'o UNITED STATES
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8 " S, ( (,g NUCLEAR REGULATORY COMMISSION g
- /..t REGION 11 o,
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101 MARIETTA ST., N.W., SUITE 3100
%,..... o ATLANTA. GEORGIA 30303 NOV 161979 In Reply Refer To:
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South Carolina Electric and Gas Company Atta:
M. C. Johnson, Vice President Special Services and Purchasing Post Office Box 764 Columbia, South Carolina 29218 Gentlemen:
The enclosed IE Information Notice No. 79-27 provides information with regard to the sequence of events that followed incidents involving steam generator tube ruptures at two PWR units.
Sincerely,
~%. k' \\
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- o.~ 7 James P. O'Reilly Director
Enclosures:
1.
IE Information Notice No. 79-27 2.
List of IE Information Notices Issued in the Last Six Months 1443 T33 7911300 [Yl
NOV 161979 South Carolina Electric and Gas Company cc w/ enc 1:
T. B. Conners, Jr.
Conners, Moore and Corber 1747 Pennsylvania Avenue, N.W.
Washington, D.C.
20006 A. A. Smith Quality Assurance Post Office Box 8 Jenkinsville, South Carolina 29065
.0. S. Bradham, Manager Nuclear Operations Post Office Box 8 Jenkinsville, South Carolina 29065
SSINS No.:
6870 Accession No.:
7910250488 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON D.C.
20555 November 16, 1979 IE Information Notice No. 79-27 STEAM GENERATOR TUBE RUPTURES AT TWO PWR PLANTS Description of Circumstances:
In recent months two incidents involving steam generator tube ruptures have occurred.
In both instances, the units were cooled down and placed in the residual heat removal mode with existing procedures.
Event of June 25, 1979, at the Doel 2 Nuclear Power Plant in Belgium The first event occurred on June 25, 1979, at the Doel 2 nuclear power plant in Belgium. The voel unit is a 390 Mwe Westinghouse two-loop reactor. The event consisted of a rupture of several tubes in the loop B steam generator. The resultant leakage between the primary and secondary systems was estimated to be 125 gpm.
The event started when the plant was heated up after a shutdown caused by a malfunction of the main steam isolation valve. At the time of the incident the primary coolant pressure was 2233 psi and the temperature 491 F.
The reactor remained suberitical throughout the event.
The first indication of abnormal behavior was a rapid decreasa of the primary system pressure (approximately:
28 psi / min.).
This was followed by the sequence of events listed below:
Time, min.
1.
Increase of charging flow dekand, charging pump.
2.
Automatic isolation of the CVCS 1 DUPLICATE DOCUMENT 3.
Shut off of the pressurizer heate Entire document previously Pressurizer.
cntered into system under:
ANO No. of pages: