ML19290E422
| ML19290E422 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point, Palisades File:Consumers Energy icon.png |
| Issue date: | 02/08/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Dewitt R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8003110117 | |
| Download: ML19290E422 (1) | |
Text
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'e UNITED STATES
- 'n NUCLEAR REGULATORY COMMISSION E
REGION lli
}\\C o
GLEN ELLYN. ILLINOIS 60137 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 Bulletin No. 80-04, is forwarded for action. A written response is required.
If you desire additional infortration regarding this matter, please contact this office.
Sincerely,
&.23 lbf yJames G. Keppler Director
Enclosure:
IE Bulletin No. 80-04 cc w/ encl:
Mr. D. P Hoffman, Nuclear Licensing Administrator Mr. C. J. Hartman, Plant Superintendent Mr. J. G. Lewis, Manager Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Ronald Callen, Michigan Public Service Commission Myron M. Cherry, Chicago 8003110 C
U!lITED STATES SSINS t'o. :
6820 NUCLEAR REGULATORY COMMISSION Accessions f;o.:
0FFICE OF INSPECTION AND EilFORCEMENT 7910250504 WASHIt;GTON, D.C.
20555 February 8, 1980 IE Bulletin f;o. 80-04 ANALYSIS OF A PWR liAIN STEA!1 LINE BREAK UITH CONTINUED FEEDUATER ADDITION Description of Circumstances:
Virginia Electric and Power Co. submitted a recort to the fluclear Regulatory Comission dated September 7,1979 that identified a deficiency in the original analysis of containment pressurization as a result of reanalysis of stean line break for florth Anna Power Station, Units 3 and 4.
Stone and Webster Engineering Cornoration performed a reanalysis of centainment pressure following a main steam line break and determined that, if the auxiliary feedwater system continued to supply feedwater at runout conditions to the stean generator that had experienced the steam line break, containment design oressure would be exceeded in approximately 10 minutes.
The long tern blowdown of the water supplied under runout conditions by the auxiliary feedwater system had not been considered in the earlier analysis.
On October 1,1979, the foregoing information was provided to all holders of operating licenses and construction permits in IE Information tlotice flo. 79-24 The Palisades facility did an accident analysis review pursuant to the information in the notice and discovered that with offsite power available, the condensate pumps would feed the affected generator at on excessive rate.
This excessive feed was not considered in the analysis for the steam line break accident.
On January 30, 1980, fiaine Yankee Atonic Power Conpany inforned the flRC of an error in the main steam line break analysis for the !1aine Yankee plant.
During a review of the main steam line break analysis, for zero or low power at the end of core life, the licensee identified an incorrect oostulation that the startup feedwater control valves would remain oositioned "as is" during the transient.
In reality, the startup feedwater control valves will rano to 80% full open due to an override signal resulting from the low steam generator pressure reactor trip signal.
Reanalysis of the event shows the opening of the startup valve and associated high feedwater addition to the affected steam generator would cause a rapid reactor cooldown and resultant return-to-power, a condition outside the plant design basis.
Actions to be Taken by the Licensee:
For all pressurized water pow reactors listed in Enclosure DUPLICATE DOCUMENT 1.
Review the containment p.
potential for containmen Entire document previously entered into system under:
ANO h
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