ML19210D782
| ML19210D782 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point, Palisades File:Consumers Energy icon.png |
| Issue date: | 11/16/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Dewitt R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 7911280063 | |
| Download: ML19210D782 (1) | |
Text
o UNITED STATES
!,,,;7 (' g NUCLEAR REGULATORY COMMISSION e
REGION lli
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f 799 ROOSEVELT ROAD
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o, GLEN ELLYN, ILLINOls 60137 b.
Docket No. 50-155 Docket No. 50-255 Consumers Power Company ATTN:
Mr. R. B. DeWitt Vice President Nuclear Operations 212 West Michigan Avenue Jackson, MI 49201 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 ur.its.
Sincerely, b*
f u
VJames G. Keppler Director
Enclosures:
1.
IE Information Notice No. 79-27 2.
Recently Issued IE Information Notices cc w/encls:
Mr. C. J. Hartman, Plant Superintendent Mr. J. G. Lewis, Manager Central Files Director, NRR/ETH Director, NRR/ DOR PDR Local PDR NSIC 1435 507 TIC Ronald Callen, Michigan Public Service Commission Anthony Roisman, Esq., Attorney Myron M. Cherry, Chicago 7911280063-
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 Calgium.
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 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 subtritical throughout the event.
The first indication of abnormal behavior was a rapid decrease of the primary system pressure (soproximately:
28 psi / min.).
This was followed by the sequence of events listed below:
Time, min.
1.
Increase of chargina flow demand, requiring startup of a second 1.8 charging pump.
2.
Automatic isolation of the CVCS 1 3.
Shut off of the pressurizer heate DUPLICATE DOCUMENT pressurizer.
1435 <M Entire document previously entered into system under:
h ANO fh No. of pages: