ML20086K528

AO 75-6:on 750119,core Spray B Line Vent Solenoid SV-4224 Found Leaking.Caused by Damaged Seating Surface of Valve. Valve Seat Replaced & Local Leak Rate Testing Completed Satisfactorily

ML20086K528
Person / Time
Site:	Peach Bottom
Issue date:	01/29/1975
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Giambusso A Office of Nuclear Reactor Regulation
Shared Package
ML20086K530	List: ML20086K528 ML20086K532
References
AO-75-6, NUDOCS 8401270204
Download: ML20086K528 (2)

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PHILADELPHIA ELECTRIC COMPANY * -

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s January 29, 1975 Mr. A. Giambusso Deputy Director of Reactor Projects s United States Atomic Energy Commission Directorate of Licensing Washington, D.C. 20545

Subject:

Abnormal Occurrence The following occurrence was reported to Mr. E. J. Brunner, A.E.C. Region 1 Regulatory Operations Office on January 19, 1975.

Written notification was made to Mr. James P. O'Reilly, Region I hgulctsry Opersticas O f ficc on Jcnuary 0,- 1975. . Ir, cccord:ncc. ad th-

'Section 6.7.2.A of the Technical Specifications, Appendix A of DPR-44 for Unit 2 Peach Bottom Atomic Power Station, the following report is being submitted to the Directorate of Licensing as an Abnormal Occurrence:

Reference:

License Number DPR-44 Technical Specification

Reference:

4.7.A.2.f Report No.: 50-277-75-6 Report Date: January 29, 1975-Occurrence Date: January 19, 1975 Faci li ty: Peach Bottom Atomic Power Station R.D. 1, Del ta, Pennsylvania 17314 1

Identification of Occurrence:

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I Core Spray "B" Line Vent Solenoid (SV-4224) leak.

Condi tions Prior to Occurrence:

Unit 2 shutdown with a maintenance outage in progress. [

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cw>Y SENT REGION -

Mr. A. Gitmbusso p pV , ,

Jrnunry 29, 1975 V Pagn 2 Description of Occurrence:

During a routine local leak rate test of the Core Spray Discharge Isolation Valves, the Core Spray "B" line vent solenoid was found to leak in excess of acceptable value.

Designation of Apparent Cause of Occurrence:

Damaged seating surface of valve.

Analysis of Occurrence:

Since this valve vents between the inboard and outboard core spray isolation valves and the normally closed inboard valve was proven to be leak tight, the safety implication of this occurrence was minimal.

Corrective Action:

The valve seat was replaced and local leak rate testing was completed satisfactorily.

Failure Data:

None previous.

Very truly yours,

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/I f M. J. Cooney '

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Ass't Gen'1 Superintendent Genera ti on Di vision cc: Mr. J. P. O' Rei l ly Director, Region 1 Uni ted States Atomic Energy Conunission 631 Park Avenue King of Prussia, PA 19406

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