ML19344D068
| ML19344D068 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 02/14/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Davidson D CLEVELAND ELECTRIC ILLUMINATING CO. |
| References | |
| NUDOCS 8003110173 | |
| Download: ML19344D068 (1) | |
Text
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UNITED STATES
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GLEN ELLYN. ILLINOIS 60137
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Docket No. 50-440 NO 14 h60 Docket No. 50-441 The Cleveland Electric Illuminating Company ATTN:
Mr. Dalwyn R. Davidson Vice President - Engineering P. O. Box 5000 Cleveland, OH 44101 Gentlemen:
Our letter dated February 8, 1980, regarding IE Bulletin No. 80-04 was in error.
It should have stated for information only.
No written response is required.
Sincerely, 0 WV n
f flamesG.Keppler V Director
Enclosure:
IE Bulletia No. 80-04 cc w/ enc 1:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Harold W. Kohn, Power Siting Commission Mr. Daniel D. Wilt, Attorney Helen Evans, State of Ohio i
/73 l
8008U 0 W
UNITED STATES SSINS t!o.: 6820 NUCLEAR REGULATORY COMiilSSION Accessions No.:
OFFICE OF INSPECTION AND Ef! FORCE 1ENT 7910250504 WASHINGTON, D.C.
20555 February 8, 1980 IE Bulletin No. 80-04 ANALYSIS OF A PNR liAIN STEAM LINE BREAK UITH CONTINUED FEED'JATER ADDITION Description of Circunstances:
Virginia Electric and Power Co. submitted a recort to the Nuclear 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 North Anna Power Station, Units 3 and 4.
Stone and Webster Engineering Corooration performed a reanalysis of centainment pressure following a main stean line break and determined that, if the auxiliary feedwater system continued to supply feedwater at runout conditions to the steam generator that had experienced the steam line break, containnent design pressure 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 infornation was provided to all holders of ocerating licenses and construction permits in IE Information Notice No. 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 an 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 Company inforned the NRC of an error in the main steam line break analysis for the !!aine 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 identiried an incorrect postulation that the startup feedwater control valves would remain positioned "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 cf 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:
y For cll pressurized water pow reacttes listed in Enclosure DUPLICATE DOCUMENT 1.
Review the containment p potential for containmen Entire document previously entered into system under:
-TT/0250EdV xNO h
No. of a es:
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