ML20086K995

Telecopy AO 74-24:on 740507,RCIC Outboard Steam Isolation Valve MO-13-16 Failed to Open Following Surveillance Test. Caused by Failed Motor.Outboard & Operable Inboard RCIC Steam Isolation Valves Placed in Closed Position

ML20086K995
Person / Time
Site:	Peach Bottom, 05000000
Issue date:	05/08/1974
From:	Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20086K988	List: ML20086K995
References
AO-74-24, NUDOCS 8402070107
Download: ML20086K995 (2)

Text

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May 8, 1974 p .

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- V d Mr. Jaces P. O'Reilly, Director '

United States Atomic Energy Comission Directorate of Regulatory Operations 631 Park Avenue Kin 6 of Prussia, Pennsylvania 19406 Subjact: Abnorml Occurrence 24-Hour Notification -

Confirming cy conversation with Mr. Tom Shedlovsky, A.E.C. Region I Regulatory Operations Office on May 6,1974.

Reference:

License Number DPR 44, Amendment Nu=ber 1 Technical Specification 3 5.D.1; 3 7.D.1 Report No.: 50-277-74-24 Report Late: May 8, 1974 Occurrance Date: May 7, 1974 Facility: Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:

RCIC outboard steam isolation valve (MD-13-16) failed to open following the performance of a surveillance test.

Conditions Prior to Occurrence: -

Plant operating at approxicately 72% power.

Designation of Occurrence: '

1 During the performance of a routine surveillance test on the RCIC system, the steam supply line was ccrrectly isolated. Both the inboard and outboard isolation valves closed as required by the testing procedure.

Following coepletion of the surveillance test, the outboard isolation '

valve could not be re-opened.

Designation of Apparent Cause of Occurrence:

An investigation perforced following the occurrence indicated that the ..

d.c. cotor circuit resietances had varied significantly from the values recorded during the pre-operational period. A brief e:ternal inspection .

of the valve and valve operator did not indicate any reason for its '

inoperability. It is presently believed that the motor on this valve opereor has failed. The location of this component in e high radiation .

area prevents further detailed investigation with the plant at significant power levels.'

Analysis of Occurrence:

The failure of this valve to open places the RCIC system in an inoperable condition. The Technical Specifications pereit continued operation of -

the plant with the RCIC syste= inoperable provided that the HPCI system is operable. The HPCI system was satisfactorily tested on $/7/74 i:x:ediately aftar this occurrence. Since sufficient emergency cooling systecs are available, there is no safety significance associated with continued operation of the plant during the short, time interval pereitted by the Technical Specifications. .

8402070107 740317 PDR ADOCK 05000277 S PDR

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. It chould be noted ,st the valve operated properly '

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- tion valve, direction. Since w a valve is also a containment a failure in the closed direction is in the fail-safe position. i- d..{.,'$^'.]

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Corrective Action:

Both the defective outboard and operable inboard RCIC steam isolation M ' .. ,. ,.

valves have been placed in the closed position. The inboard valve Qt N !

ahall remain closed until the outboard valve har been repaired and tested. $3.i ..'M ~. ,

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W. T. Ullrich, Superintendent p" < . '

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YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT C CONNECTICUT RR # 1. DOX 127E. EAST HAMPTON. CONN. o6424 May 6, 1974 CYH-2650 Mr. James P. O'Reilly, Director Region 1 Directorate of Regulatory Operations U. S. Atomic Energy Commission 631 Park Avenue King of Prussia, Pennsylvenia 19406 Dear Mr. O'Reilly; As defined by Technical Specifications for Connecticut Yankee Atomic Power Station, Section 5.3, the following information involving failure of the 2B Emergency Diesel Generator during a routine monthly surveillance test is hereby reported as abnormal occurrence 74-8.

Shortly before the completion of the monthly load test of 2B ,

Emergency Diesel Generator as required by Section 4.5A of the Technical Specification, smoke was observed coming from the associated control censole. The test run was suspended and the diesel unit shutdown. C02 was discharged into the console to extinguish any ignited material.

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Investigation revealed that one of the three field excitation transformers (one per phase) had overheated and burned a hole in the transformer winding approximately one and one-half inches in diameter.

Damage was also indicated in the connecting wiring for the affected transformer.

The affected transfonner was removed pending receipt of a replacement.

The remaining two transformers were removed and tested satisfactorily.

Necessary replacements and wiring repair will be accomplished promptly.

An investigation of the failure cause is continuing with the Vendor.

The remaining Emergency Diesel Generator will be operated in accorddnce with the Technical Specifications pending repair completion. A final report will be submitted within ten days.

Very truly yours, k .

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Q.Y.Hhrtleyi t

Plant Superintendent b

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