ML19310A462

LER 80-018/01P-0:on 800611,leakage Developed in Feedwater Line.Plant Shutdown to Cold Condition Initiated.Caused by Failure of Feedwater Check Valve Bonnet Seal.Seal Will Be Repaired Prior to Resuming Operation

ML19310A462
Person / Time
Site:	Vermont Yankee
Issue date:	06/12/1980
From:	Murphy W VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19310A461	List: ML19310A460 ML19310A462
References
LER-80-018-01P, LER-80-18-1P, NUDOCS 8006170595
Download: ML19310A462 (2)

Text

NRC F ohm 366 U. S. NUCLE AR REGULATORY COMMISSION i i

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LICENSEE EVENT REPORT LER 80-18/IP (PLE ASE PRINT OR TYPE ALL REQUIRED INFORMATION) v

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l o l ai l9 l vl TLICENSEEl v 1CODE Y l S l 1 l@l 0 l 0 l - lLICENSE 14 lb 0 l 0NUMBEH l0l0l0l-l0 26 l 0 26 l@l 4 l 1TYPE LICENSE l

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74 75 REPORT DATE 80 7 8 60 61 DOCK ET NUMB E R EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h Io12l lDuring a planned drywell entry to investigate suspected reactor coolant leaks. operatorb PTTTl lobserved that leakage had developed in one of the feedwater lines. An orderly plant I l o 14 l lshutdown to cold conditions was immediately initiated. Further investigation of the l l O l s il l eak revealed that a significant portion of it was flowing directly into the Torus via l I O 16 I lthe vent header. Since this flow path bypasses the drvwell leakage detection system, I l 0 f 71 lit was determined that this situation constitutes a condition not specifically considerf-1Olailed in the Safety Analysis Report or the Technical Specifications. 80 I

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10 12 13 18 19 20 7 8 11 SE OVE NTI AL OCCURRENCE REPORT REVISION

. EVENT YE AR REPORT NO. CODE TYPE N O.

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R RO l8 l0 l [J [0l1l8l l/l l0l1l lPl b l0 l 32 21 22 23 24 26 27 28 29 30 31 AK f AC 0 ON L NT ME HOURS S8 i FOR B. SU PLI MAN F CTURER lXl@lXl@ W@ [36A_J@ l0 l0 l 3 l0 l W@

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JJ J4 35 3e 40 43 CAUSE DESCRIPT!*)N AND CORRECTIVE ACTIONS l1 I O l l The cause of the event is attributed to an apparent inadecuacy in the desien of the I i i I drywell leakage detection system. The immediate corrective action will he en nAminin-l

, 7 (tratively reduce the limits of Tech. Spec. Section 3.6.C to allow only 2 1/2 gpm l

, ., l 1eskage from unidentified sources and 12 1/2 gpm from the total reactor coolant systemi, g l In addition, the occurrence will be further evaluated to determine if other correctivel 7 8 9 (Continued on attached sheet.60

'ST'ANS

% POWER OTHER STATUS @ DISCCO RY DISCOVERY DESCRIPTION @

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ACTIVITY CO$ TENT AMOUNT OF ACTIVITY LOCATION OF RELEASE i 6 NA l l NA l 7

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PE RSONNE L iNJuNiES NUV8ER DESCR4 TION @

NA l li la 8l l9 Ol Ol Ol@l12 7 11 80 LOSS OF OR DAM AGE TO F ACILITY TYPE DESCRIPTION 9 (_Zj@l NA l 7 8 9 10 80 e

ISSUE DESCRIPTION 7

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NAME OF PREPARER PHONE:

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'05000271

, LER 80-18/IP CA'USE DESCRIPTION AND CORRECTIVE ACTIONS measures are necessary. The feedwater leak was determined to be a failure of the feedwar check valve bonnet seal, which will be repaired prior to resuming normal operations.

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