ML19290E440
| ML19290E440 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Byron, Braidwood, Quad Cities, LaSalle  |
| Issue date: | 02/14/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Reed C COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8003110244 | |
| Download: ML19290E440 (1) | |
Text
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NUCLEAR REGULATORY COMMISSION c
REGION lli
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799 ROOSEVELT ROAD 3,
GLEN ELLIN ILLINOIS 60137
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FEB 14 580 Docket Nos. 50-10, 50-237, 50-249, 50-254, 50-265, 50-373, 50-374, 50-454, 50-455, 50-456, 50-457 Commonwealth Edison Company ATTN:
Mr. Cordell Reed Vice President Post Office Box 767 Chicago, IL 60690 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, eO James G. Keppler Director i
Enclosure:
IE Bulletin No. 80-04 cc w/ enc 1:
Mr. D. L. Peoples, Director Central Files of Nuclear Licensing Director NNR/DPM Mr. B. B. Stephenson, Director NNR/ DOR Station Superintendent PDR Mr. N. Kalivianakis, Local PDR Plant Superintendent NSIC Mr. L. J. Burke, Site TIC Project Superintendent Mr. Dean Hansell, Office of Mr. T. E. Quaka, Quality Assistant Attorney General Assurance Supervisor Mr. R. H. Holyoak, Station Mr. Gunner Sorensen, Site Superintendent Project Superintendent Mr. R. Cosaro, Project Superintendent 8003110 ED
UtilTED STATES SSItiS tio.: 6820 ICJCLEAR REGULATORY COMlilSSION Accessions f;o.:
OFFICE OF I!iSPECTION A!iD Et: FORCE'tEili 7910250504 WASHIfGT0tl, D.C.
20555 February 8, 1980
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IE Bulletin fio. 80-04 ANALYSIS OF A PMR !!AIN STEA!; LINE BREAK L'ITH CONTINUED FEEDUATER ADDITION Description of Circunstances:
Virginia Electric and Power Co. submitted a report to the fluclear Regulatory Comission dated September 7,1979 that identified a deficiency in the original analysis cf 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 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 systen 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 flotice flo. 79-24.
The Palisades facility did an accident analysis review pursuant to the information in the notice and discovered that with offsite power avaibble, 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, flaine Yankee Atomic Power Company inforned the f!RC of an error in the main steam line break analysis for the fiaine 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 positioned "as is" durino the transient.
In reality, the startup feedwater control valves will rano to 80% full open due to an override signal resulting from the 'ow 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 stean 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:
h ANO h
No. of pages: