ML19318C800

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Responds to IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Reanalysis of Reactivity Increase Will Be Submitted by 800516.Containment Pressure Response Analysis Is Being Performed by Vendor
ML19318C800
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 05/08/1980
From: William Jones
OMAHA PUBLIC POWER DISTRICT
To: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
IEB-80-04, IEB-80-4, NUDOCS 8007020299
Download: ML19318C800 (2)


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1623 MARNEY e OMANA. NEsRASMA 68102 e TELEPHON E S 36-4000 AREA CODE 402 May 8, 1980 Mr. K. V. Seyfrit, Director U. S. Nuclear Regulatory Commis:sion Office of Inspection and Enforcement Region IV 611 Ryan Plaza Drive Suite 1000

, Arlington, Texas 76011

Reference:

Docket No. 50-285

Dear Mr. Seyfrit:

The Omaha Public Power District received IE Bulletin 80-04, dated February 8, 1980, requesting an analysis of a PWR Main Steam Line Break (MSLB) with continued feedvater addition from the auxiliary feedvater system. The analysis was to include an evaluation of containment pres-sure response and resultant reactivity increase from the MSLB.

The reanalysis of the reactivity increase, as required by item 2 of the bulletin, will be submitted to the Conmission by May 16, 1980. The analysis has been completed by our reactor vendor, but not received by the District. As requested by item 3 of the bulletin, please note the vender has confirmed that tne analysis results indicate the return-to-power is not versened by assuming continued feedvater addition for the MSLB.

The containment pressure response analysis, requested in item 1 of the bulletin, is presently being performed by our reactor vendor. An analysis for MSLB pressure response has not been performed to date for the Fort Calhoun Station, thus requiring a completely new analysis to be conducted. The District has been advised it vill be available for submittal to the Commission by June 30, 1980.

It should be noted that a generic analysis applicable to the Fort Calhoun Station has been performed by our reactor vendor which provides assurance that containment pressure remains within acceptable limits with continued auxiliary feedvater flow during a MSLB inside containment.

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Mr. K. V. Seyfrit May 8, 1980 Page Two This analysis, submitted to the Commission by letter dated January 10, 1980, is entitled "Best Estimate MSLB Analysis to Assess NSSS and Containment Response With Automatic Auxiliary Feedwater Actuation (CE-18074-706)".

Sincerely, IfI(h r~ +0G5 ,

W. C. Jones Division Manager Production Operations WCJ/KJM/BJH/TLP:jmm cc: U. S. Nuclecr Regulatory Commission Office of Inspection and Enforcement >

Division of Reactor Operation Inspection Washington, D. C. 20555 LeBoeuf, Lamb, Leiby & MacRae i 1333 -New Hampshire Avenue, N. W. -

Washington, D. C. 20036 l