ML20086J092

AO 75-1:on 750102,inboard Main Steam Line Sample Isolation Valve Appeared to Be Not Fully Closed.Caused by Bent Position Indication Actuation Arm.Arm Straightened,Limit Switch Adjusted & Valve Stroked

ML20086J092
Person / Time
Site:	Peach Bottom
Issue date:	01/12/1975
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Giambusso A Office of Nuclear Reactor Regulation
Shared Package
ML20086J095	List: ML20086J092 ML20086J101
References
AO-75-1, NUDOCS 8401230171
Download: ML20086J092 (2)

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f January 12, 1975 Mr. A. Giambusso Deputy Director of Reactor Projects United States Atomic Energy Commission Directorate of Licensing Washington, DC 20545

Dear Mr. Giambusso:

The following occurrence was reported to Mr. Wal t Baunack, A.E.C. Region 1 Regulatory Operations Office on January 3, 1975 Written notification was made to Mr. James P. O'Reilly, Region 1 Regu-latory Operations Of fice on January 3,1975 In accordance with Section 6 7.2.A of the Technical Specifications, Appendix A of DPR-56 for Unit 3 Peach Bottom Atomic Power Station, the following report is being submitted to the Directorate of Licensing as an Abnormal Occurrence:

Re fer ence: License Number DFi<-56 Technical Specification: 3 7.D Report No.: 50-278-75-1 Report Date: January 12, 1975 Occurrence Date: January 2, 1975 Facility: Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identificatien of 0:currence:

Unit 3 inboard main steam line sample isolation valve appeared to be not fully closed.

Conditions Prior to Occurrence:

The reactor was operating at 95 1% power. Startup testing was in progress.

Description of Occurrence:

It appeared that the inboard main steam line sample isolation valve (inside the drywell) would not isolate when the control switch was placed in the close position. The outboard isolation valve was immediately closed.

8401230171 750112 PDR ADOCK 05000278 S PDR T Jt ' t. I' r

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Mr. A. Giambusso January 12, 1975 Page 2 Designatien of Apparent Cause of Occurrence:

The valve was found to close properly; the position indi-cation actuation arm was found to be bent.

Analysis of Occurrence:

Both isolation valves were verified to close properly. Only valve position indication failed to operate correctly. For this reascn, the occurrence has no safety implications.

Corrective Action:

As required by the Technical Specifications, a daily log of the other operable isolation valve was immediately instituted in the form of an established surveillance test which verifies that the posi-J tion of the other isolation valve (in the same line) is in the closed or isolated condi t ion. The positior. indication actuation arm was straightened, the limit switch was adj'.sted to reduce the bending e f fec t on the arm, and the valve was stroked several times sucess- j fully. A local leak rate test was performed; the leakage rate was Zero.

Failure Data:

A previous f ailurc of this type was reoorted as Abnormal Occurrence Report Number 50-278-74-15 Very truly yours,

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M J. Cooney A s't Gener Superintendent Generation Division cc: Mr . J. P. O' Reil ly Director, Region i United States Atomic Energy Commission 631 Park Avenue King of Prussia, PA 19406

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