ML20050E252

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Third Interim Deficiency Rept of Significant Const Deficiency 25 Re Defective GE Circuit Breakers (AKR-30 & AKR-50) Originally Reported 811203.Reinstalltion & Testing to Be Completed by 820430.Final Rept by 820714
ML20050E252
Person / Time
Site: Waterford Entergy icon.png
Issue date: 04/01/1982
From: Mclendon G, Milhiser R, Wills J
LOUISIANA POWER & LIGHT CO.
To: Jay Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, W3K-82-0192, W3K-82-192, NUDOCS 8204130146
Download: ML20050E252 (3)


Text

LOUISIANA 142 ORARONDE STRUT POWER & LIG HT P O BOX 6008 NEW ORLEANS LOUISIANA 70174 . (504) 366 2345

'Yu?Es SSYIr5 u

April 1,1982 G. D. McLENDON Senior Vice President

( W3K 0192 Q-3-A35.07.25 Mr. John T. Collins, Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012

SUBJECT:

Waterford SES Unit No. 3 Docket No. 50-382 Interim Status Report of Significant Construction Deficiency No. 25

" Defective GE Circuit Breakers (AKR-30 and AKR-50)"

Third Interim Report

Reference:

LP&L Letter W3K-81-0436 to USNRC dated December 3, 1981

Dear Mr. Collins:

In accordance with the requirements of 10CFR50.55(e), we are hereby submitting two copies of the Interim Status Report of Significant Construction Deficiency No. 25, " Defective GE Circuit Breakers (AKR-30 and AKR-50)".

If you have any questions, please advise.

Very truly yours,

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Attachment FIECElvgo 9 cc: 1) Director D APR1219825 k Office af Inspection & Enforcement ts u w ryyyy s ,

U. S. Nuclear Regulatory Commission 9, QEdCm Washington, D. C. 20555 /, & /

(with 15 copies of report) q,f

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2) Director 1l

/

Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C. 20555 (with I copy of report) 8204130146 820401 PDR ADOCK 05000382 S PDR

LOUISIANA POWER & LIGHT COMPANY WATERFORD SES UNIT NO. 3 Third Interim Status Report of Significant Construction Deficiency No. 25

" Defective GE Circuit Breakers (AKR-30 and AKR-50)"

Reviewed by M J/ [L R. J. Mi r - Site Manager Date Reviewed by 8/ 2 J ills - Project Superintendent " Date' Reviewed by M AA GE, Eh w,rg 3/ S2.

J. Hart - P ject Licensing Engineer / Dat'e Reviewed by U D 33/8I.*

W. Yae

- Sr. E side t En ineer ' Date Reviewed by ~ ~h ~

5 3/!/L bate J. Gutierrez - . A. Site Supervisor /

March 30, 1982 l

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THIRD INTERIM STATUS REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 25

" DEFECTIVE GE CIRCUIT BREAKERS (AKR-30 AND AKR-50)"

INTRODUCTION This report is submitted pursuant to 10CFR50.55(e). It describes potential failures in the General Electric AKR-30 and AKR-50 Low Voltage Power Circuit Breakers supplied to the Waterford 3 project. This problem is considered reportable under the requirements of 10CFR50.55(e). To the best of our knowledge, this problem has not been identified to the Nuclear Regulatory Commission pursuant to 10CFR21.

DESCRIPTION General Electric AKR-30 and AKR-50 Low Voltage Power Circuit Breakers purchased from GE between mid-1976 and December 19, 1980, have been tested by GE, and in a limited number of instances, the electronically operated AKR-50 Low Voltage Power Circuit Breakers have failed to close upon command. Failure occurred after the circuit breaker had been left in the charged position for several hours. The cause of the failure was traced to deformation of a lead Teflon sleeve serving as a bearing in the breaker.

GE was not aware of any failure in the AKR-30 Circuit Breakers, but the AKR-30 uses the same lead Teflon sleeve and may be subject to the same failure mode.

SAFETY IMPLICATIONS These breakers have been installed in the 480V switchgear. Failure of these breakers to close can inhibit safety-related equipment from operating and thus compromise the safe shutdown of the plant.

CORRECTIVE ACTION Eighty-one (81) of eighty-six (86) breakers have been repaired. During the repairs, five (5) breakers were found to have other damaged parts which required repair by GE at their facility. These five breakers have been repaired and returned to the site for reinstallation. They will require inspection upon receipt and in-plant testing to check out their functionability. This will necessitate having a GE technical representative present at the site to witness this testing. Completion of their reinstallation and testing is anticipated to occur by April 30, 1982; and a Final Report will be submitted to the USNRC by May 14, 1982.

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