ML20084G060

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AOs 50-244/73-06 & 50-244/73-07:on 730722,sensing Line on Auxiliary Feedwater Pump B Failed,Causing Reactor Trip. Caused by Disconnected Line on Discharge Valve.Sensing Line for Pump B Reworked
ML20084G060
Person / Time
Site: Ginna Constellation icon.png
Issue date: 08/01/1973
From: Green G
ROCHESTER GAS & ELECTRIC CORP.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20084G063 List:
References
AO-50-244-73-06, AO-50-244-73-07, AO-50-244-73-6, AO-50-244-73-7, NUDOCS 8304210385
Download: ML20084G060 (4)


Text

- _ _ _ _ _ _ _ _ _ ______________________________ -__

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August 1,1973 Mr. James P. O'Reilly, Director Directorate of Regulatory Operations Region I United States Atomic Energy Commission 631 Park Avenue King of Prussia, Pennsylvania 10406

Subject:

R. E. Ginna Nuclear Power Plant, Unit No.1 '

Failure of sensing line on "B" Auxiliary Feedwater Pump Abnormal occurence 73-6 and 73-7 Docket No. 50-244

Dear Mr. O'Reilly:

In accordance with Technical Specifications Section 6.6.2a which requires that a written report relative to abnormal occurrences be submitted within ten days to the Director of Licensing with a copy sent to the Director of Regional Regulatory Operations, the fonowing is submitted:

A reactor trip occurred at 1306 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.96933e-4 months <br /> on July 22, 1973. The trip signal which was activated was a combination of low steam generator level and feedwater flow-steam flow mismatch associated with the "B" steam generator. The low steam generator level and feedwater flow-steam flow mismatch has been attributed to the separation of the "B" steam generator feedwater control valve " plug" from the valve stem. During the transient, piping displacement was sufficient enough to cause a "Swagelock" fitting associated with the "B" auxiliary feedwater flow orifice and dp guage to disconnect.

The normal performance of the auxiliary feedwater pump is as follows:

a) During power operation, the discharge valve of the auxiliary feedwater pump is open.

b) Following initiation of a signal for the pump to start, the pump will start and the discharge valve will, if closed, open wide.

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c) The flow transmitter accociated with the feedwater pump then supplies a signal to the discharge valve to throttle back to a flow of approximately 230 gpm.

During the transient, the pump started automatically. The disconnection of the Dow transmitter crea'.ed a false high flow signal which caused the auxiliary feedwater pump discharge valve to stroke toward the closed position.

, The operator noted from control board instrumentation that there was high

) flow and high discharge pressure readings associated with the "B" auxiliary feedpump. The operator determined that the high discharge pressure indicated low flow from the auxiliary feedwater pump and manually opened the discharge valve to provide flow to the steam generator. An auxiliary operator was dispatched to inspect the pump and he isolated the disconnected

, line. This malfunction is believed reportable under the abnormal occurrence definition as written in Technical Specifications section 1.0d which states:

" Failure of one or more components of an engineered safety feature or plant protection system that causes or threatens to cause the feature or system to be incapable of performing its intended function. "

It must be noted that due to the concentration of effort into the investigation of the causes and of the transient which occurred, this event was not reported within the twenty-four hour specifications defined by the Technical Specifications. Only in subsequent post incident review and discussion by and with the operators involved and by further inspection of the feedwater lines did this situation become evident. Therefore, it is further believed that this item be reported as an abnormal occurrence as defined by Technical Specifications 1.0g as follows: " Observed inadequacies in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause the existence or development of an unsafe condition in connection with the safe operation of the plant. "

This event was reviewed and discussed by the Plant Operations Review Committee on July 20, 1973. The following modifications were approved and performed: ,

The sensing lines for the flow transmitters for the "B" auxiliary feedwater pump were evaluated and it was determined that there was not sufficient expansion capability for the piping displacement that was experienced. The sensing line for the "B" auxiliary feedwater pump was reworked to include expansion bonds to allow for such piping displacements. Furthermore, the rigidity of the support for the sensing lines was improved and one additicnal anchor to the wall was added. This was installed on July 28,1073.

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re. r - August 1,1973

. m ,rMr. James P. O'Rc{J, Director O 3 5

Similar expansion bonds were added to the "A" auxiliary feedwater pump flow sensing lines on July 29, 1973.

To ensure that all personnel give due consideration to the Technical Spcifications relative to abnormal occurrences, the Plant Superintendent has posted a letter to all personnel reminding them of their personal responsibility in proper and timely reporting of plant abnormalities.

It is intended that the above actions will preclude the recurrence of these events.

Vqry truly yours, l 0/

, r . p~C"t Grang#;m /

et . Green Vice Presi[ent Electric and Steam xc:Mr. John F. O' Leary 4

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Licensce: RocL_Acr Gas and Electric Corporation

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.:,. H. D. Thornburg, out Docket No.: 50-244

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  • i Abnormal Occurrenec: A0 73-6 and 13-7 l i ; 1o (Name and waits smiti ALs a t na am as

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DR Central Files (1) om The attached report from the subject licensee is Regulatory Standards :3)

Dir. of Licensing (131 foruarded in accordance uith no Manual chnnter 1onn iROo (n.m..no e,.inus umms Files of Central Ma'i1 & Files The action taken by the li_censee is considered l' nn appropriato. Follouup uill be performed during i,,

the next inspection ds appronriate. Confessof I. FitcM (Name anJ unit) MMARR$

j. / '/ the report have been foruarded to the PDR, Local t ,A l

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R. T. ,o,arlson, Chief PT*, NSIC, DTIE and Stato representativos. The

  • Facili / Operations Jr:m ch lic.cncee will submit a 10 day written report to PHDM 960 Daft 8/3/73 Licensing.
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