ML19210A225

Abnormal Occurrence 50-289/75-30:on 750827,valve CF-V-2B of Core Flood Tank B Sample Line Isolation Failed to Close Upon Receipt of Engineered Safeguards Actuation Signal.Caused by Valve Binding Against Valve Stem

ML19210A225
Person / Time
Site:	Three Mile Island
Issue date:	09/05/1975
From:	Arnold R METROPOLITAN EDISON CO.
To:
References
GQL-1482, NUDOCS 7910240938
Download: ML19210A225 (5)

Text

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INCIDEfr NRC DISTRIBUTION FOR PART 50 DOCKE " MATERI AL (TEMPORARY FORM)

CONTROL NO: W FILE: INCIDE!TE REFORT FIL:

FROM:'detropolitan Edicsn Co.

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1 c0-M0 DESCRIPTION:

ENCLOSURES:

A/O 4 75-30, en 5-27-75, Ccncerning Failure of Core Flood Tank "3" Sanple line Isolatica Valve (CF-7-23) to close on an Engineered Safeguards x

Actuation Signal....

(1 Copy Enclosure Feceived)

PLANT NAME:

Three Mle Island FOR ACTION /INFORMATION SA3 0-12-75 BUTLER (L)

SCHWENCER (L) ZIEMANN (L)

REG AN (E)

W/ Copies W/ Copies W/ Copies W/ Copies DO NOT REMi OVE CLARK (L)

STOLZ (L)

DICKER (E)

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W/ Cooies W/ Cooies W/ Cocies

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VASSALLO (L)

KNIGHTON (E)

SPELS ACKNOWLEDGED W/ Copies W/ Copies W/ Copies W/ Copies KNIEL (L)

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CHAPMAN

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-Regulaterf b< ? G'l' METROPOLITAN EDISON COMPANY PCF cFCICE SOX 542 REAc!NG. PENNSYLV ANI A 19CC3 TELEPNCNC 215 - S29 :CM Septe=ber 5, 1975-GQL lhS2 s

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Divisien of Reacter Licensing s

U. S. Nuclear Regulatcry Cc==ission J7 ' ' ', ',_js.

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Docket No. 50-289 Cperating License No. DPR-50

Dear Sir:

In accordance with the Technical Specifications of cu-Three Mile Island Nuclear Station Unit 1 (3I-1), we are reperting the folleving abncr=al occurrence.

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5 (1) Report Number: A0 50-209/75-30

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eces-a (2a) Report Date: September 5, 1975

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L cCPIOl376.# hl, (2b) Cccurrence Date: August 27, 19T5 l=

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(3) Fac ility : Three Mile Island Nuclear Staticn Unitt 1

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Identification of Occurrence:

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Title:

Failure of Core Flecd Tank "B" Sample line Iselaticn Valve (CF-7-23) to close on an Engineered Safeguards Actuation Signal Type:

An abncr=al occurrence as defined by the Technical Specificaticns, paragraph 1.8d, in that fail re of CF-7-23 to close constituted a failure of one ec=penent of an engineered safety feature that threatened to cause that feature to ce incapable of performing its intended function.

(5) Canditiens Pricr to Occurrence:

Power: Core:

99",

Elect.. 326 Mwe (Grces)

F RC Flev:

139x10' lb/hr 306 259 RC Fress:

2155 psig RC temp:

580*T

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.TO: Directcr Division of eeacter Licensing U. S..'iuclear Eegulatcry Cc==issicn FRZR level:

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r (6) Cescription of Cecurrence:

At 1130 hcurs en August 27, 1975 while perfer=ing the Reactor Building Cooling and Isolation Cc=penent and Lcgic Surve.llance Test, CF-V-23 (Cere Flced Tank "3" Sample Line Isolation Valve) failed te close upcn receipt of an Engineered Safeguards actuation signal.

I:=ediately pricr to this failure, the valve operated satisfactcrily upon receipt of two separate auto Engineered Safeguards test actuaticn signals.

An attempt was made to close CF-V-23 using the re=cte pushbutton, but the valve failed to close.

CF-V-23 was then clcsed locally by use of its handwheel, after which the valve cycled prcperly using the re=cte pushbutton.

The redundant isolaticn valve for the sa=ple line CF-V-23 was cycled to verify its operability.

CF-V-2B was manually cycled and the valve stem lubricated. An inspection was made of the valve's auxiliary contact b1ceks to deternine if they were binding the opening and closing contacters in any way.

(7) Designatien cf Apparent Cause of cecurrence:

Initial investigation indicated CF-V-23 failed to close as a result of the valve packing binding against the valve stem, causing it to stcp travel by cpening the clcsing terque switch prematurely.

Further troubleshcoting revealed that CF-V-23 may have failed to close due to the closing torque switch apparently physically being held cpen intermittently by splice insulating caps asscciated with viring located next to the switch. The viring adjacent to the switch provides 120 VAC to the valve limit switch cc=partment heater which is used to re=cve moisture. Excess vire asscciated with the heater was coiled in close prcximity to the valve cicsing torque switch contacts, hence the interference of the wire insulating caps with the switch contacts may have in turn caused the valve not to fully close. It is postulated that either cne or both of the above proble=s caused the closing torque switch contacts to open early, preventing CF-V-23 frc= cicsing.

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' 'TO : Directcr Divisicn of Eeacter Licensing U. S. Nuclear Regulatcry Cennissicn

- (8) Analysis of Occurrence:

It is believed that the failure of CF-7-23 did not represent a threat to the health and safety of the public in that:

a.

Cne containment isolatien valve is sufficient to isolate the Core Flood Tank "3" Sample Line in the event of a less of ecolant accident.

b.

The redundant centain=ent isolation valve for the Cere Flced Tank "3" Sa=ple Line was cperable.

c.

The redundant isolatien valve was closed at the ti=e of the occurrence.

(9) Corrective Acticns:

In additicn to the corrective actions =entioned abcVe 1cng term corrective actions were:

CF-V-23's torque switch settings have been increased, yet a.

are within acceptable linits, and any wires that '.culd possibly interfere with proper torque switch contact operation have been relecated.

b.

The valve CF-7-23 vill be repacked to further reduce the possibility of any abncr=al binding.

The Plant Opersticus Review Cenmittee and the Station Superintendent have reviewed and approved the above listed ccrrective acticns and have taken steps to ensure cc=pletion of the yet to be ec=pleted long tern corrective actions.

(10) Failure Data:

Valve Cperatcr:

Limitorque SME-000 Valve:

Ecekvell 362h(F316)JM Type-Globe 1,

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'"C : Director Division of Reactcr Licensing U. S. Nuclear Regulatory Cc=issien

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Similar Occurrences: :icne Sincerely, 0

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R. C. AR:ICLD 7 ice President RCA :C'4S :rk cc: Office of Inspection and F.Nforcement, Region 1 File: 7 7 3 5 1/20.1.1 1476 262