ML20086J037

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

ML20086J037
Person / Time
Site:	Peach Bottom
Issue date:	02/11/1975
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Giambusso A Office of Nuclear Reactor Regulation
Shared Package
ML20086J040	List: ML20086J037 ML20086J045
References
AO-75-8, NUDOCS 8401230065
Download: ML20086J037 (2)

Text

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l February 11, 1975 Mr. A. Giambusso Director, Division of Reactor Licensing Office of Nuclear Reactor Regulations United States Nuclear Regulatory Commission Wa shi ng ton, D.C. 20555

Subject:

Abnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, N.R.C. Region 1 Office of Inspection and Enforcement on February 2, 1975. Written notification was made to Mr. James P. O'Reilly, Region 1 Office of Inspection and Enforcement on February 3,1975. In accordance wi th Section 6.7.2.A of the Technical Speci fica tions, Appendix A of DPR-56 for Unit 3 Peach Bottom Atomic Power Station, the following report is being submitted to the Directoraie of Reactor Licensing as an Abnormal Occurrence: -

Reference:

License Number DPR-56 Technical Specification Reference 4.7.A.2.f Report No. 50-278-75-8 Report Date: February 11, 1975 Occurrence Date: February 1, 1975 Faci li ty: Peach Bottom Atomic Power Station R.D. ni, Delta, Pennsylvania 17314 Identification of Occurrence:

Excessive leakage of RCIC inboard steam supply valve (MO ,

Conditions Prior to Occurrence:

Unit 3 shutdown for piping inspection.

Description of Occurrence:

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

8401230065 750211 b7, gDRADOCK 05000278 PDR 5sd J n, ?d COPY SENT REGION nw

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February 11, 1975 4 Page 2 Designation of Apparent Cause of Occurrence:

Worn packing.

Analysi s of Occurrence:

The safety implications of this occurrence are minimal since the outer isolation valve, M0-3-13-16 was found to leak no more than 120cc/ minute.

Corrective Action:

The valve was repacked. Local leak rate testing was per-formed following the repacking and indicated a negligible leak rate.

Failure Data:

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

Very truly yours, 7,w M. . Cooney Asst. Gen 1. Superintendent Generation Division cc: Mr. James P. O'Reilly Director Office of Inspection and Enforcement Region 1 United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

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