ML20087D497

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First Interim Significant Const Deficiency Rept 99 Re Safety Injection Tank Isolation Valve Mechanically Binding,Causing Valve Motor to Trip on Overload.Valve Actuator Inspected, Repaired & Tested.Final Rept by 840406
ML20087D497
Person / Time
Site: Waterford Entergy icon.png
Issue date: 02/29/1984
From: Gerrets T
LOUISIANA POWER & LIGHT CO.
To: Jay Collins
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
99, W3K84-0433, W3K84-433, NUDOCS 8403130427
Download: ML20087D497 (3)


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O LOUISIANA / n2 o nanoNoe sin m POWE R & LiG H T/ P O BOX 6008 + NEW ORLEANS. LOUtslANA 70174 . (504) 366-2345 ISNEYSE February 29, 1984 W3K84-0433 Q-3-A35.07.99 33@ BOWS T Mr. John T. Collins Regional Administrator, Region IV

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b U. S. Nuc3 r Regulatory Commission p 611 Ryan .

  • Drive, Suite 1000 "

I Arlington, ts 76012

REFERENCE:

Telecon C. N. Hooper (LP&L) and W. Crossman (NRC IV) on January 20, 1984

Dear Mr. Collins:

SUBJECT:

Waterford SES Unit No. 3 Docket No. 50-382 Significant Construction Deficiency No. 99

" Safety Injection Tank (SIT) Isolation Valve" First Interim Report In accordance with the requirements of 10CFR50.55(e), we are hereby providing two copies of the Interim Report of Significant Construction Deficiency No.

99, " Safety Injection Tank (SIT) Isolation Valve." This item was previously identified as PRD No. 143.

If you have any questions, please advise.

Very truly yours, KC T. F. Gerreta Corporate Quality Assurance Manager TFG:CNH:VBR Attachment cc: Director Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 (15 copies) 8403130427 840229 PDR ADOCK 05000302 S PDF

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.Mr. John T.' Collins February 29, 1984 W3K84-0433 Page 2 cc: Director Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. E. L. Blake Shaw, Pittman, Potts, & Trowbridge 1800 M Street, N.W.

Washington, D.C. 20036 Mr. W. M. Stevenson Monroe & Lemann-1424 Whitney Building New Orleans, Louisiana 70130 >

Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway,' Suite 1500 Atlanta, Georgia' 30339

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e; INTERIM REPORT OF SIGNIFICANT CONSTRUCTION DEFICIENCY NO. 99

" SAFETY INJECTION TANK (SIT) ISOLATION VALVE"

' INTRODUCTION This report;is submitted pursuant to 10CFR50.55(e). It describes a deficiency in the performance requirements of the Safety Injection Tank (SIT) Isolation Valve .1SI-V1507'TK2A (SI-332A) supplied by the Lunkenheimer Corporation with a Limitorque Corporation Actuator.

TS the best of our knowledge, this deficiency has not been reported to the USNRC pursuant to 10CFR21.

DESCRIPTION During Preoperational Testing, SIT Isolation Valve ISI-V1507 TK2A (SI-332A) appeared to mechanically bind, causing che valve motor to trip on overload.

Inspection of the valve actuator found a broken motor pinion gear, stripped worm gear, and broken retainer ring.

FSAR Section 6.3.2.2.1 requires that this valve open on demand from an SIAS

-when'the RCS pressure islless than 400 psig. This function ensures that the tank will discharge automatically during a LOCA.

SAFETY IMPLICATION 1he valve in. question'is. locked open when RCS pressure is increased above 500 psig during normal power: operation.- During plant cooldown and shutdown

. cooling, the SIT pressure is reducedoto 377_psig when RCS pressure decreases

'below 650 psig. .When RCS pressure is below 400 psig, the SIT isolation valve

will- be cloegd. _ Upon SIAS, this valve is required to automatically open.

Therefere, if left uncorrected, the failure of this valve could result in the inability to-automatically discharge into the RCS following a'depressurization event.

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CORRECTIVE AJTION '

",.[ TheLyalve~ actuator has been inspected, repaired, and tested. Actuator components which failed are unavailable for material testing. A Final Report will be issued pending an inspection and evaluation by a Lunkenheimer

-Corporation Representative.-

A status of-Final Report will be submitted to the USNRC on or before

-- . April 6,-1984.

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