ML20086E124

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AO 73-20:on 730706,drywell Purging & Vent Exhaust Valve V16-19-7A Would Not Close.Inoperability Exceeded Limiting Conditions for Operation.Reactor Shut Down & Cooling Down at Time of Incident
ML20086E124
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 07/06/1973
From: Riley B
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20086E119 List:
References
AO-73-20, VYV-2781, NUDOCS 8312060067
Download: ML20086E124 (2)


Text

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. O a > VEIu1ONT YANKElc NUCLEAR power CORPOR ATION O

h SEVENTY GCVEN OROVC STRCCT RUTI,AND, VeintoNT osvoi VYV-2781 P.O.DOX 157 VERNON. VERMONT 05354 July 6, 1973 United States Atomic Energy Commission Directorate of Regulatory Operations,. Region T 970 Broad Street Newark, New Jersey 07102

REFERENCE:

Operating License hPR-28 Docket No. 50-271 Abnormal Occurrence No. A0-73-20 Centlemen:

As defined by Technical Specifications for the Vermont Yankee Nuclear Power Station, Section 6.7.B.1, we are reporting the following Abnornal Occurrence as A0-73-20 and confirming our telephone conversation with your office.

At 0800 on July 6, 1973, while purging the drywell via RTF-5, V16-19-4, and V16-19-7A, the Drywell Purging and Vent Exhaust Valve V16-19-7A would not close. The inoperability of Valve V16-19-7A exceeds the Limiting Conditions for Operation as defined by Section 3.7. A.2 of the Technical Specifications. The subject section states that Primary Containment Integrity shall be maintained at all times when the reactor is critical or when the reactor water temperature is above 212*F and f uel is in the reactor vessel. The reactor was shutdown and cooling down at the time of the incident. Reactor temperature was 300*F and reactor pressure was 50 psig.

Very truly yours, VERMONT YANKEE NUCLEAR P0'JER CORPORATION Bradford U. Riley ^ -

Plant Superintendent \

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yem nt Yankee Nucicar Power Corp.

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Licensec:

. 50-271

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  • D* Thornburg. g A0-73-20 Chicf. FS6EB Abnomal Occurrence:

S o g ,,, ,,s. .,o,o RO:1!Q (5) om The attached report from the subject licensce is DR Central Files (1)

Reguintory Standards '3) forwarded in accordance with RO Manual chnoter 1060 Dir. of Licencing (13t n-ans t o m.m. .no .,.y u inic The action taken by the licensee is considered RO Files ~

Central Mai1 & Files appropriate. Followup will be performed during rut I.

Confes nf i

t the next insucction a's annro9riate.

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F ROM (td.ru e and waiu the report have been foruarded to the PDR, Local

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The PDR, NSIC, DTIE and Stato representatives.

R. T. Carlson, Chief Facility Operations licensco will submit a 10 day written report to

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