ML19290E448
| ML19290E448 | |
| Person / Time | |
|---|---|
| Issue date: | 02/14/1980 |
| From: | Carroll D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 8003110264 | |
| Download: ML19290E448 (3) | |
Text
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UNITED STATES l'
s.([j NUCLEAR REGULATORY COMMISSION
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ctEu Ettvu. ittinois soia7 FEB 14 1gge State of Illinois Department of Public Health ATTN:
Mr. Gary N. Wright, Chief Division of Nuclear Safety 535 West Jefferson Street Springfield, IL 62761 Gentlemen:
The enclosed IE Bulletin No. 80-04 titled " Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition" was sent to the following licensees on February 8, 1980 for:
ACTION American Electric Power Service Corporation Indiana and Michigan Power Company D. C. Cook 1, 2 (50-315, 50-316)
Commonwealth Edison Company Zion 1, 2 (50-295, 50-304)
Consumers Power Company Palisades (50-255)
Northern States Power Company Prairie Island 1, 2 (50-282, 50-306)
Toledo Edison Company Davis-Besse 1 (50-346)
Wisconsin Electric Power Company Point Beach 1, 2 (50-266, 50-301)
Wisconsin Public Service Corporation Kewaunee (50-305) s 8003110 EO
flb i s is. j State of Illinois
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INFORMATION Cincinnati Gas & Electric Company Zimmer (50-358)
Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441)
Commonwealth Edison Company Braidwood 1, 2 (50-456. 50-457)
Byron 1, 2 (50-454, 50-455)
Dresden 1, 2, 3 (50-10, 50-237, 50-249)
La Salle 1, 2 (50-373, 50-374)
Quad-Cities 1, 2 (50-265)
Consumers Power Company Big Rock Point (50-155)
Midland 1, 2 (50-329, 50-330)
Dairyland Power Cooperative LACBWR (50-409)
Detroit Edison Company Fermi 2 (50-341)
Illinois Power Company Clinton 1, 2 (50-461, 50-462)
Iowa Electric Light & Power Company Duane Arnold (50-331)
Northern Indiana Public Service Company Bailly (50-367)
Northern States Power Company Monticello (50-263)
II I980 I
State of Illinois Public Service of Indiana Marble liill 1, 2 (50-546, 50-547)
Union Electric Company Callaway 1, 2 (50-483, 50-486)
Sincerely, Lc
./ a t Le L(
D rothy E.
arroll, Acting Chief Administrative Branch
Enclosure:
IE Bulletin No. 80-04 cc w/ encl:
Mr. D. W. Kane, Sargent & Lundy Central Files Reproduction Unit NRC 20b Local PDR NSIC TIC
UNITED STATES SSINS fio.:
6820 fiUCLEAR REGULATORY COMMISSION Accessions No.:
OFFICE OF INSPECTION AND Ef70RCEMENT 7910250504 WASHINGTON, D.C.
20555 February 8, 1980 J
J IE Bulletin f;o. 80-04 ANALYSIS OF A PWR fiAIN STEAfi LINE BREAK UITH CONTINUED FEEDuATER ADDITION Description of Circunstances:
Virginia Electric and Power Co. subnitted a recort to the fluclear Regulatory Comission dated September 7,1979 that identified a deficienc.v 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 steam generator that had experienced the steam line break, containnent design pressure would be exceeded in approximately 10 minutes.
The long tern blowdnwn 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 2rnits in IE Information flotice flo. 79-24.
The Palisades facility did an accic._at 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, flaine Yankee Atomic Power Company inforned the flRC of an error in the main steam line break analysis for the Maine Yankee plant.
During a review of the main steam line break analysis, for zern 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 trantient.
In reality, the startup feedwater control valves will rano 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 nasis.
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:
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