ML19210D796
| ML19210D796 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/16/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| References | |
| NUDOCS 7911280083 | |
| Download: ML19210D796 (1) | |
Text
/
UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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799 ROOSEVELT ROAD g, *....f s<
GLE N E LLYN, ILUNOls 60137 Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company ATTN:
Mr. Sol Burstein Executive Vice President Power Plants 231 West Michigan Milwaukee, WI 53201 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, s
- James G. Keppler Director
Enclosures:
1.
IE Information Notice No. 79-27 2.
Recently Issued IE Information Notices cc w/encls:
Mr. C. A. Reed, Plant Manager Central Files Director, NRR/DPM Director, NRR/ DOR C. M. Trammell, ORB /NRR PDR Local PDR NSIC j d j 'Q' j}j TIC Sandra A. Bast, Lakeshore Citizens for Safe Energy 79112 80 g
SSINS No.:
6870 Accession No.:
7910250488 UNITED STATES NUCLEAF. REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON D.C.
20555 November S, 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 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 between the primary and secondary systems was estimated to be 125 gpm.
The event started when the plant was heated up af ter 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 subcritical 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 3.
Shut off of the pressurizer heat pressurizer.
DUPLICATE DOCUMEqT 7, r5 t3p Entire document previously entered into system under:
ANO No. of pages: