ML19290E450
| ML19290E450 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/14/1980 |
| From: | Carroll D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8003110270 | |
| Download: ML19290E450 (3) | |
Text
[pa arc %[o, TIC UNITED STATES
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NUCLEAR REGULATORY COMMISSION 3
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REGION 111 o,,h'1/./, f 799 ROOSEVE LT ROAD
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GLEN ELLYN. ILLINOIS 60137 4 *...*
FEB 141980 MEMORANDUM FOR:
Those on Attached List FROM:
Dorothy E. Carroll, Acting Chief, Administrative Branch
SUBJECT:
IE BULLETIN NO. 80-04 The attached 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)
INFORMATION Cincinnati Gas & Electric Company Zimmer (50-358)
Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441) 8003110 3 70
Those on Attached List -
flu 1% iddd 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 Inulana Public Service Company Bailly (50-367)
Northern States Power Company Monticello (50-263)
Public Service of Indiana Marble Hill 1, 2 (50-546, 50-547)
Union Electric Company Callaway 1, 2 (50-483, 50-486) y'
.ar'r 1 Ac n lief Administ ative Branch
Enclosure:
Addressees - Memorandum dated February 13, 1980 IE Files MPA/DTS Central Files Reproduction Unit NRC 20b
UNITED STATES SSINS No.:
6820 NUCLEAR REGULATORY COMMISSION Accessions No.:
0FFICE OF INSPECTION AND ENFORCEMENT 7910250504 WASHINGTON, D.C.
20555 O
February 8, 1980 IE Bulletin No. 80-04 ANALYSIS OF A PWR MAIN STEA!' LINE BREAK UITH CONTINUED FEEDUATER ADDITION Description of Circumstances:
Virginia Electric and Power Co. subnitted a recort to the Nuclear Regulatory Comission dated September 7,1979 that identified a deficier y 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 Cornoration perforned 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 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 t!otice 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, flaine Yankee Atonic Power Company inforned the NRC 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 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 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 dt,ign basis.
Actions to be Taken by the Licensee:
For all pressurized water pow reactors listed in Enclosure 1.
Review the containment p potential for containmen Entire document previously entered into system under:
ANO No. of es: