ML19261F290

Abnormal Occurrence 50-289/74-15:on 740911,during Quarterly Surveillance of Reactor Bldg Cooling & Isolation Sys Logic, Spray Valve BS-V1B Failed to Open.Caused by Improperly Installed Wire.Wire Removed & Blown Fuse Replaced

ML19261F290
Person / Time
Site:	Three Mile Island
Issue date:	09/20/1974
From:	Arnold R METROPOLITAN EDISON CO.
To:
References
GQL-0344, GQL-344, NUDOCS 7910250741
Download: ML19261F290 (4)

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• 0-289 DESCRIPTION: . E';CLCSU?lS :

Ltr re Abnormal' Occurrence #74-15 on 9-11-74

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• cFFICE BOX 542 RE AclNG, PENNSYLVANI A 19603 TELEPwCNE 215 - 329 : Col SEP 2 01974 Regulatory Decket File os Osuu Director Directorate of Licensing U. S. Atc=ic Energy Co==ission Washingten, D. C. 20545 tear Sir:

Operating License DPR-50 Decket No. 50-289 In accordance with the Technical Specifications fcr Three Mile Island Nuclear Station, Unit 1, we are reporting the folleving abnormal occur-rence:

/' k (1) Report Nu=ber: A0 50-289/7h-15 (2c) Report Date: Cepte=ber 20, 1974 hkU TAk 3 r (2b) Occurrence Date: Septe=ber 11, 197h 14 SEP N 7979 @\

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(3) Facility: Three Mile Island Nuclear Statien, Unit 1 C.) c fQ' '--;

.i (k) Identification cf Occurrence:

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Title:

Inability of the Reactor Building Spray Valve BS-V13 to Open During Test Type: An abncr=al occurrence as defined by the Technical Specifi-cations, paragraph 1.8d, in that che inability of the Reactor Building Spray Valve BS-VlB t) cpen thrcatened to cause an Engineered Safeguard feature er system to be incapable of performing its intended i'uncticn.

(5) Ccnditiens Prior to Occurrence: The reactor was at steady state power with =ajor plant parameters as follows :

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Power: Core: 75% -

-Q' k' Elec: 655 W (Gross) } kh RC Flev: Ikh x 10 lbs/hr b d'$f

Directerate of Licensing SEP 2 01974 RC Pressure: 2155 psig RC Te=p.: 579 F FR2R Level: 260 in.

PRZR Temp.: 650 F (6) Description of Occurrence: At 1500 hcurs en Septe=ter 11, 197h, while the quarterly surveillance of the Reacter Building Cooling and Isolation System logic was being perfor=ed, Reactor Building Spray Valve BS-V13 did not respend to an open signal because of a blevn centrol fuse. The valve did open when two other autc=atic 1cgic channels and the manual actuatien were tested.

(7) Designation of Apparent Cause of Occurrence: It has been dete:::ined that the cause of the occurrence was an improperly installed wire in an Engineered Safeguards Actuatien System Lcgic Panel in cen-junction with a spurious ground on the 1A statien battery. The existence of these cenditicus plus an Engineered Safeguards actuatica signal permitted a never-before-encountered current path to ground. The current flov which resulted vas, in turn, sufficient to cause the centrol fuse to blev. It is believed that the i= prop-erly installed wire was the result of a manufacturing error.

(8) halysis of Occurrence: It is believed that the failure of Reactor Building Spray Velve BS-VlB to open did not represent a threat to either the health or safety of the public in that Spray Valve BS-VlA and the redundant spray pu=p system associated with it were still available in the event an accident had cecurred.

(9) Corrective Acticn:

The folleving shcrt-ter= corrective acticas were taken in the crder given:

a. The imprcperly installed vire was re=oved, thus correcting the faulty viring conditiens; and the ground identified and ccrrected.

b. The blown fuse was replaced.

c. The affected spray valve was tested and was fcund to perfer=

satis factorily .

At a meeting b-1d in=ediately after the incident was reported, the Plant Operaticns Revf v Cec =ittee (FORC) reviewed aid approved the above corrective actions and reccc= ended to the Staticn Superintendent that in addition a detailed visual inspacticn cf tne viring in all of the Engineered Safeguards Actuation Syste= Legie Cacinets be perfor ed to deter =ine the existence of any =anufacturer errors.

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Directc. ate of Licensing SEP 2 0 $74 The Statien Superintendent cencurred with FCEC's recc==endaticn and has directed the recc== ended corrective action to be taken.

(10) Failure Data:

a. Previous Failures: Nene.

b. Equipment Identificaticn:

Engineered Safeguards Actuatica Syste= Lcgic Cc net SA A. O. Smith Ccrporatien Clark Centrol Division.

Sincerely,

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.< .'irnold Vice President ECA:JFV:sh File 7 7 3 5 1 20.1.1 cc: Mr. J. P. O'Reilly Directorate of Regulatory Operations, Region 1 U. S. Atc=ic Energy Cc==ission 631 Park Avenue King of Prussia, Pennsylvania ISkO6

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