ML20086H919
| ML20086H919 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/09/1975 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Anthony Giambusso Office of Nuclear Reactor Regulation |
| References | |
| AO-75-26, NUDOCS 8401200348 | |
| Download: ML20086H919 (2) | |
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g May 9, 1975 li. A. Giambusso, Director Division of Reactor Licensing Office of Nuclear Reactor Regulations United States Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Giambusso:
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Subject:
Abnormal Occurrence The following occurrence was reported to Mr. Walt Baunack, Region 1, Office of Inspection and Enforcement, United States Nuclear Regulatory Commission on May 1, 1975 Written notification was made to Mr. James P. O'Reilly, Region I, Of fice of Inspection and Enforce-ment, United Stetes Nuclear Regulatory Commission on May 1, 1975 In accordance with Section 6.7.2.A of the Technical Specifications, Arredix ^ ef OPR 56 fcr '!..lt 3.%s Out Lum ALo.uic Fower nation, the following occurrence is bein'3 submitted to the Directorate of Reactor Licensing as an Abnormal Occurrence.
ReferenEc:
License Number DPR-56 Technical Specification
Reference:
4.7.A.2.f Report No.:
50-278-75-26 Report Date:
May 9, 1975 Occurrence Date: April 30, 1975 Facility:
Peach Bottom Atomic Power Station l
R.D. 1, Delta, Pennsylvania 17314 L
Identification of Occu rence:
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l Excessive leakage of S.V. 3671C on penetration N-51C.
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_ Conditions Prior to Occurrence:
l' Unit 3 at approximately 100% power.
Description of Occurrence:
y R
During a routine local leak rate test of the dryweli 02 analyzer
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sample isolation valves, this inboard isolation valve was found to leak in excess of 2000 cc/ min.
8401200348 750509 d
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Mr. A. Giambusso 50 - ?78 2t.
May 9, 1975
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Designation of Apoarent Cause of Occurrence:
Disassembly of the valve indicated scoring on the seating surface which prevented the valve from seating tightly.
Analysis of Occurrence:
The safety implicption of this occurrence is minimal since the outboard isolation valve S.V. 3978C was found to operate satisfactorily and be leak tight.
In addition, the upstream manual isolation valve was closed to preclude any leakage until the valve was repaired and retested.
_ Corrective Action:
This valve was dis-assembled, the internals were cleaned, and the valve seat was re oted.
The valve was re-assembled and sub-sequent leak testing of Se valve was successful, i
Failure Data:
t Two previous failures of this valve have been reported as A0-50-278-75-ll and al so on 11/9/73 T
Very truly yours, W/
M /J. Cooney /
A s't Gen't Superintendent Generation Division
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t Mr. J. P. O'Reilly, Director cc:
Region 1 Of fice of Inspection and Enforcement i
United States Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 l
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