ML19253C180
| ML19253C180 | |
| Person / Time | |
|---|---|
| Site: | Perkins, Cherokee  |
| Issue date: | 11/16/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Dail L DUKE POWER CO. |
| References | |
| NUDOCS 7911300107 | |
| Download: ML19253C180 (2) | |
Text
l Q
/
'o UNITED STATES 8
g 3
NUCLEAR REGULATORY COMMISSION E ).. oE REGION 11
'Ii'[o*
o, 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 NOV 161979 In Reply Refer To:
RI JP0 J0-4 A8F 0-4
- -M,1) 0-492,'50-493)
Duke Power Company Attn:
L. C. Dail, Vice President Design Engineering Post Office Box 33189 Charlotte, North Carolina 28242 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,
- N'y 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 1443 2 0 7 ea s soo ' 07
NOV 161979 Duke Power Company
- cc w/ encl:
J. T. Moore, Project Manager Post Office Box 422 Gaffney, South Carolina 29340 1443 291
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 Cir estances:
In recent months two incidents involving steam generator tube ruptures have occurred.
In both instances, the units were cooled down
.d 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 everit 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 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 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 deman charging pump.
2.
Automatic isolation of the CVCS DUPLICATE DOCUMENT 3.
Shut off of the pressurizer hea Entire document previously pressurizer.
entered into system under:
ANO No. of pages: