ML19344D069
| ML19344D069 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/14/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Dewitt R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| References | |
| NUDOCS 8003110176 | |
| Download: ML19344D069 (1) | |
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UNITED STATES o
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NUCLEAR REGULATORY COMMISSION 150 g
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799 ROOSEVELT ROAD
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GLEN ELLYN. ILLINOIS 60137 Docket No.50-15s FEB 1e r:0 sumers Power Company nTTN:
Mr. R. B. DeWitt Vice President Nuclear Operations 212 West Michigan Avenue Jackson, MI 49201 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, uh' James G. Keppler Director
Enclosure:
IE Bulletin No. 80-04 cc w/ encl:
Mr. C. J. Hartman, Plant Superintendent Mr..D. P. Hoffman, Nuclear Licensing Administrator Central Files Director, NRR/DPM Director, NRR/ DOR PDR.
Local PDR NSIC TIC Ronald Callen, Michigan Public j
Service Commission 8008110 l%
1
UNITED STATES SSINS No.:
6820 NUCLEAR REGULATORY COMMISSION Accessions No.:
0FFICE OF INSPECTION AND EllFORCE!iENT 7910250504 4
WASHINGTON, D.C.
20555 February 8, 1980 IE Bulletin No. 80-04 ANALYSIS OF A PHR ItAIN STEAf1 LINE BREAK UITH CONTINUED FEEDUATER ADDITION Description of Circumstances:
l Virginia Electric and Power Co. submitted a report to the Nuclear P.egulatory Comission dated September 7,1979 that identified a deficiency in the original j
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 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, containment design pressure would be exceeded in approximately 10 minutes. The long tern blowdown of the l
water supplied under runout conditions by the auxiliary feedwater system had t
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 Notice No. 79-24.
The Palisades facility did an accident analysis review pursuant to the information in the notice and discovered that ith offsite power available, the condensate pumps would feed the affected gnerator at an excessive rate.
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This excessive feed was not considered in the a talysis for the steam line break accident.
On January 30, 1980, flaine Yankee Atomic Power Company inforned the NRC of an error in the main., team line break analysis for the fiaine Yankee plant.
During a review of sne 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" during the transient.
In reality, the startup feedwater control valves will ramo to 80% full open due to an override signal resultina 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
No. of es:
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