ML20086K520

AO 75-7:on 750119,inboard RCIC Steam Supply Valve MO-2-13-15 Found to Leak.Caused by Two Minor Surface Scratches in Valve Seat.Valve Seat & Disc Maintained to Remove Minor Surface Scratches

ML20086K520
Person / Time
Site:	Peach Bottom
Issue date:	01/29/1975
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Giambusso A US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20086K523	List: ML20086K520 ML20086K524
References
AO-75-7, NUDOCS 8401270193
Download: ML20086K520 (2)

Text

r , T PHILADELPHIA ELECTRIC COMPANY

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January 29, 1975 u Mr. A. Giambusso '

Director, Division of Reactor Licensing Office of Nuclear Reactor Regulations ,

U. S. Nuclear Regulatory Commission '

Washington, DC 20555-

Subject:

Abnormal Occurrence The following occurrence was reported to Mr. E. J. Brunner, N. R. C. Region 1, Reactor Operations Branch on January 19, 1975 Written notification'was made to Mr. James P. O'Reilly, Region 1,

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Office of Inspection and Enforcement on Januar~y 20, 1975 In accordance with 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 Reactor Licensing as an Abnormal Occurrence. '

Reference:

License Number DPR-44 Technical Specification

Reference:

4.7.A.2.f Repor t No.: 50-277-75-7 Report Date: January 29, 1975 Occurrence Date: January 19, 1975 Facility: Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314

_I_dentification of Occurrence:

Inboard RCIC Steam Supply Valve (M0 13-I S) leaks.

Conditions Prior to Occurrence:

Unit 2 shutdown; a maintenance outage is in progress.

Description of Occurrence: l-During a routine local leak rate test of the RCIC steam supply valves, M0-2-13-15 was found to leak in excess of 2000 cc/ min.

8401270193 750129 PDR ADOCK 05000277 S .ts, ;. .y. a-pyg

Mr. A. Giambusso January 29, 1975 .

Page 2 Designation of Apparent Cause of' Occurrence:

The cause for this increased valve leakage appeared to be the .

result of two minor surface scratches in the valve seat.

Analysis of Occurrence:

The safety implications of this occurrence are minimal since the outer isolation valve, MO-2-13-16, was found to be leak tight.

Corrective Action:

The valve seat and disc were maintained to remove minor surface scratches. Local leak rate testing after the repair indicated a negligible Icakage rate.

Very truly yours, Q'O {$liefC<,

t M. J. Cooney [

Ass' t Gen' t Superintendent Generation Division i

cc: Mr. James P. O'Reilly Director o Office of Inspection and Enforcement Region i United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 eh G

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