ML19210D801
| ML19210D801 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/16/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Koester G KANSAS GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7911280093 | |
| Download: ML19210D801 (1) | |
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION O%
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n.,..s November 16, 1979 In Reply Refer To:
RIV Docket No.
STN 50-482/IE Information Notice No. 79-27 Kansas Gas & Electric Co.
Attn:
Mr. Clenn L. Koester Vice President-Operations Post Office Box 208 Wichita, Kansas 67201 Centlemen:
The enclosad IE Information Notice provides information with regard to the sequence of events that followed incidents involving steam generator tube ruptures at two PWR unita.
Sincerely,
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du KarlV.S(yfrit~
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Director
Enclosures:
1.
IE Information Notice 79-27 2.
Recently Issued IE Information Notices cc: w/ enclosures Messrs. Nicholas A. Petrick, SNUPPS D. T. McPhee, Kansas City Power and Light Company Gerald Charnoff, Shaw, Pittman, Potts & Trowbridge E. W. Creel, Kansas Gas and Electric Company Toneso 04 3
SSINS No.:
6870 Accession No.:
791025048h UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON D.C.
20555 IE Information Notice No. 79-27 Date: November 16, 1979 Page 1 of 7 STEAM GENERATOR TUBE RUPTURES AT TWO PWR PLANTS Description of Circumstances:
In recent months two incidents involving eteam generator tube ruptures have occurred.
In both instances, the units were cooled down and pinced 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, et the Doel 2 nuclear power plant in Belgium.
The Doel 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 betweer. the primary and secondary systems was estimated to be 125 gpm.
The event started whm. 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, requiring startup of a second 1.8 charging pump.
2.
Automatic isolation of the CVCS letdown line.
2.4 3.
Shut off of the pressurizer heaters due to low liquid level in the 2.4 pressurizer.
4.
Closing of block valves in the pressurizer relief line.
4.6 5.
Rapid increase of water leve The steam generator was icol 6.
Startup of the third chargin DUPLICATE DOCUMENT 5
538 all charging pumps from the tank.
Entire document previously entered into system under:
7 25o ANO No. of pages:
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