ML20086J045

Telecopy AO 75-8:on 750201,excessive Leakage Found on RCIC Inboard Steam Supply Valve MO-3-13-15.Caused by Worn Packing.Valve Replaced

ML20086J045
Person / Time
Site:	Peach Bottom
Issue date:	02/03/1975
From:	Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20086J040	List: ML20086J037 ML20086J045
References
AO-75-8, NUDOCS 8401230072
Download: ML20086J045 (1)

Text

2 '

- 4 & -; . -

c . u _ _ _ -_ _ - - A

{l l

O v Ci l

I

. PL.Eas E D El-IUEl l PPILADELPHIA ELECTRIC COMPANY Peach Bottom Atomic Power Station ggy ggg; l5 ,

Delta, Pennsylvania l' 17314

,' February 3, 1975

!! Mr. James P. O'Reilly, Director l! United States Atomic Energy Con::nission Dircctorate of Regulatory Operations 631 Park Avenue -

.t King of Prussia, Pennsylvania 19406 Subjcet: Abnormal Occurrence 24-Hour Notification Confirming W. T. Ullrich's phone conversation with Mr. Walt Baunack, A.E.C. Region 1

- Regulatory Operations Office on February 2, 1975.

qw . .? ,s s Refcrence: 1.icense Number DPR-56 4' ' ' ' c's Technical Specification

Reference:

4.7.A.2.f 1_' ~ l b , '

D )M d ,\

.i Rrport No.: 50-278-75-8 - , J. . . 7.2 ;

'~#

.t R p3rt Date: February 2, 1975 --

' b 'j

) Occurrence Date: February 1, 1975 ~~

I Fccility: Peach Bottom Atomic Power Station R.D. 1. Delta, Pennsylvania 17314 "

,e - f/

1 ' Q.; , - e ,/

Identification of Occurrence: -

Ezeg;::ive 12:h g: ef ECIC 1:h: rd ::::= cupply velve (MO-3-13-15).

C2nditions Prior to Occurrence: -

I Unit 3 shutdown for piping inspection.  ;

l J Description of Occurrence:

During a routine local leak rate test of the RCIC steam supply valves, MO-3-13-15 was found to leak in excess of 2000 cc/ min.

i _D signation of Apparent Cause of Occurrences jY Worn packing.

i i Analysis of Occurrence:

The safety implications of this occurrence are minimal since the combined leakage thru both valve seats (HO-3-13-15 and H0-13-13-16) was found to be approximately 120 cc/ min.' f ,

Corrcetive Actions -

The valve was replaced. Local le..n. rate tcsting was performed and the leakage was

' found to be 120 cc/ min. This is an acceptable leak rate. -

Failure Data:

A previous failure of this type was reported as Abnormal Occurrence Report Number 50-277-75-7.

8401230072 750211 PDR ADOCK 05000278 .

S PDR V?ry truly yours.

1402 W

< E T. Ullrich, Superintendent i Caanh Bettom Atomic Power Station

. . . _ __- ..