ML19253C189
| ML19253C189 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/16/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Hanock J FLORIDA POWER CORP. |
| References | |
| NUDOCS 7911300124 | |
| Download: ML19253C189 (2) | |
Text
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'o, UNITED STATES 8
g [,g NUCLEAR REGULATORY COMMISSION j
,., e REGION II o
/i' t
101 MARIETTA ST., N.W., SUITE 3100
%,.../
g' ATLANTA, GEORGIA 30303 NOV 161979 In Reply Refer To:
RII-302,)
Florida Power Corporation Attn:
J. A. Hancock, Director Nuclear Operations P. O. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733 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 P'a'R units.
Sincere 1.y,
~
Tk., ~,
James P. O'Reill Director
Enclosures:
1.
IE Information Notice No. 79-27 2.
List of IE Information Notices Issued in the Last Six Months
) L\\ b} b i2M 7911300
'i
NOV 101979 Florida Power Corporation.
cc w/ enc 1:
G. P. Beatty, Jr.
Nuclear Plant Superintendent Post Office Box 1240 Crystal River, Florida 32629
SSINS No.:
6870 Accession No.:
7910250488 UNITED STATES NUCLEAR REGULATORY C0tiffISSION OFFICE OF INSPECTION AND ENFORCErfENT WASHINGTON D.C.
20555 November 16, 1979 IE Information Notice No. 79-27 STEAM GENERATOR TUBE REPIURES AT TWO PWR PLANTS Description of Circumstances:
In recent months two incidents involving steam generator tube ruptures have occurred.
In both instancer, the units vere cooled down and placed in the residual heat removal mode with existing procedures.
Event of June 25, 1979, at the Doel 2 Nuclear Power Plar.t in Belgium The first event occurred on June 25, 1979, at the Doel 2 nuclear power plant in Belgium. The Doel unit is a 390 Hwe 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 decrease 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 demand, r-~ i-4--
~^
charging pump.
2.
Automatic isolation of the CVCS le
) 4 4)
.b
)
3.
Shut off of the pressurizer heater pressurizer.
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