ML20086D803

AO 73-07:on 730302,steam Leak Noted Around Bonnet of Steam Exhaust Line Check Valve.Hpci Exhaust Line Stop Check Valve Gagged Shut,Check Bonnet Gasket Replaced & Bonnet Retightened

ML20086D803
Person / Time
Site:	Vermont Yankee
Issue date:	03/05/1973
From:	Riley B VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20086D797	List: ML20086D795 ML20086D803
References
AO-73-07, AO-73-7, ASO-730305, VYV-2485, NUDOCS 8312050127
Download: ML20086D803 (2)

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VERMONT Y NKEE NUOLDAO POWH3t CORPORATION

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ocvenry seven crove evac Rurtwo, Venowr os70:

VYV - 2485 P.O. BOX 187 vennon, vemeour osas4 March 5, 1973 United States Atomic Energy Commission Directorate of Regulatory Operations, Region 1 970 Broad Street Newark, New Jersey 07102 REFERENCE Operating License DPR-28 Docket Ho'. 50-271 Abrormal Occurrence No. A0-73-07 Gentlement An defined by Technical Specifications for the Vement Yankee Nuclear Power Station, Section 6.7.A.c, we are reporting the following Abnormal Occurrence as /4-73-07 and confirming our telephone conversation with your office.

At approximately 2300 on March 2, 1973 during conduct of an operability check of the High Pressure Coolant Injection (HPCI) System, a steam Isak was noted around the bonnet of the steam exhaust line check valve (HPCI-65) . Although the HPCI systess was observed to be operable, repair of the check valve was elected as an itamediate course of action. Replacement of the hasket precluded HPCI operability as required by Section 3.5.E.1.s of Technical Specifications. The reactor was operating at approximately 60% power at the time of this incident.

The HPCI exhaust line stop check valve was gagged shut and the check valve bonnet gasket was replaced and the bonnet retightened.

Concurrently, the operability verification required by Cection 4.5.B.2 of Technical Specifications was initiated. At 0230 on March 3, 1973 the HPCI operability test was repeated catisfactorily, and no leakage was detected from the bonnet of HPCI-65.

Very truly yours.

VERMONT YANKEE JUCLEAR POWER CORPORATION fl Y&

Bradford W. Riley  %

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J Plant Superintendant h DWE/sms 8312050127 730309 PDRADOCKOS000g S

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Licens_ce: VERMONT YANILEE NUCLE.*.R PWER CMP.

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Dil ( ent ral rile: (1) c ra ~ ~ - -The attached report from the subject liccusee is ite,ulatory Standards 3)

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the report have been forwarded to the PDR, Local db \ Y ___ PDR, USIC, DTIE and State representatives. The

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_ _ _ licensee will submit a 10 day written report to Pee M sal 1, D.1:3 /6/73 Licensing.

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