ML20082S932

First Interim Significant Const Deficiency Rept 93 Re Failure of Valve 1CH-F-2501 A/B (CVC-103) to Close Following Hot Functional Testing.Vendor Repaired Valve by Installing New Seats.Further Testing Recommended.Next Rept by 840217

ML20082S932
Person / Time
Site:	Waterford
Issue date:	12/02/1983
From:	Gerrets T LOUISIANA POWER & LIGHT CO.
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, 93, W3K83-1880, NUDOCS 8312150066
Download: ML20082S932 (3)

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LOUISIANA 20WE R & LIG H T /Waterford 3 SES/P. O. Box B/Killona, LA 70066 December 2, 1983 W3K83-1880 Q-3-A35.07.93 kc,-

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PLMGIMIJWIK 1 l

I, Mr. John T. Colline Regional Administrator, Region IV g'

ggg ll, U. S. Nuclear Regulatory Commission i

611 Ryan Plaza Drive, Suite 1000

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Arlington, Texas 76012 l

REFERENCE:

Telecon C. Hooper (LP&L) and W. Crossman (USNRC) of November 4, 1983

SUBJECT:

Waterford SES Unit No. 3 Docket ~No. 50-382 Significant Construction Deficiency No. 93

" Charging and Letdown Containment Isolation Valve Deficiency" First Interim Report In accordance with 10 CFR 50.55(e), attached are two copies of the interim response to Significant Construction Deficiency No. 93, " Charging and Letdown Containment Isolation Valve Deficiency." This item was previously identified as PRD No. 129.

Very truly yours, T. F. Gerrets Quality Assurance Manager TFG:CNH:SSTG Attachment cc.

Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C.

20555 (15 copies) 8312150066 831202 PDR ADOCK 05000392 S

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Mr. John T. Collins December 2, 1983'

. W3K83-1880 j-Page 2 q:

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-Office of Management C,

Information and Program Control l.

U. S. Nuclear Regulatory Commission Washingtou, D.C.

20555

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Mr. E. L. Blake j

Shaw,.Pittman, Potts, & Trowbridge i

1800 M Street N.W.

I Washington, D.C.

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l Mr. W. M. Stevenson Monroe & Lemann

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1424 Whitney Building i

New Orleans,. Louisiana 70130 l

Records Center-l Institute of Nuclear Power Operations l

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1100 Circle 75 Parkway, Suite-1500~

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f Atlanta, Ceorgia 30339 l

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g-INTERIM REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 93

" CHARGING AND LETDOWN CONTAINMENT ISOLATION VALVE DEFICIENCY"

. INTRODUCTION-

.This report is submitted' pursuant to 10 CFR 50.55(e).

It describes the failure of valve ICH-F-2501 A/B (CVC-103) to close following Hot Functional Testing'(HFT). This problem is considered reportable under the requirements

-of 10 CFR 50.55(e).

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To the~best of our knowledge, this deficiency has'not been reported to the

. TIMNRC nitrminant to - 10 CFR 21.--

y DESCRIPTION OF PROBLEM' Follewing the cooldown after RFT, it was discovered'that that valve 1CH-F-2501 A/B (CVC-103), (supplied by.WKM), was ' stuck in the open position. This valve had been. exposed to 550*F service temperature for several days during HFT of' the' charging and Ir. n system.

It appears that'the malfunction occurred due to the upstresa float of the seat which reduced the clearance between the seat.and the gate, thereby-causing the gate to stick open.

' SAFETY EVALUATION Valves 1CH-F2501.A/B (inside Containment, powered from SB division) and

.1CH-F-1518 A/B (outside Containment, SA division) provide Containment isolation for the letdown line. Failure of ICH-F-2501 A/B to close would, if-left uncorrected, violate the requirements of GDC55. Although there is in fact 'another safety Class 1 valve (ICH-F-1516 A/B) upscream of the 'affected

> valve 1CH-F-2501 A/B), which would automatically close on high containment pressure or low pressurizar pressure, it is powered from the SA division. The requirements for independent power sources would therefore,~not'be met if valve ICH-F-2501 A/B failed to close.

CORRECTIVE ACTION Vendor service technician (WKM) has repaired the valve with new seats which are sized for maximum interference fit in the seat pocket in order to eliminate the previously experienced seat float. The valve has since been

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' satisfactorily' tested in'the cold fluid condition.

Further testing has been recommended to verify the proper operation of this valve during' hot fluid conditions and the subsequent cooldown. An update or final report will be submitted to the USNRC on or before February 17,-1984.

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