ML19210A175

Abnormal Occurrence 75-17:on 750615,during Test of Reactor Bldg Purge Isolation Valve Local Leak Rate Test,Two Exhaust Valves Would Not Pressurize to Required Test Pressure.Caused by Valve AH-V1A Failing to Fully Close

ML19210A175
Person / Time
Site:	Three Mile Island
Issue date:	06/17/1975
From:	Herbein J METROPOLITAN EDISON CO.
To:
References
NUDOCS 7910240898
Download: ML19210A175 (2)

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• BC r ;~ A NETROPOLITAN EDISON COMPANY sussiosany or cenean rueuc uriuries coaron arson TELEPHONE 717 944 4041 37 CPPtCE BOX 480 MIDDLETOWN,PENNSYLVANTA 17057 June 17,1975 Mr. J.P. O'Reilly, Director ao ,

,IrI N. .j D

Directorate of Regulatory Operations i Region I ov]Jd (jld #

631 Park Avenue King of Prussia, Pa. 19406 Operating License 07R-50 Docket 5,0-289 ,

Subject:

Abnormal Occurrence No. A0 _75-17,

Dear Mr. O*Reilly:

This telegram is to confim the telecon between Lee Spessard. Region I-ERC, and J.J. Colitz (TMI Unit 1 Superintendent) at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> 16 June 1975.

The following report is submitted in accordance with paragraph 6.7.2.a.2 (page 6-11) of the technical specifications.

During the annual Reactor Building)Parge isolation valves local leak testing (S.P. 1303-11.18 Section D 4.4.1.2.5.c the interspace between purge exhaust valves AH-V1A is AH-V1B ceuld not be initially pressurized to the required test pressure of 55 psi.

This imlicated possible Reactor Guilding Local Leakage in excess of the limit set in technical specification 4.4.1.2.3. .

Visual inspection revealed that AH-VIA was not fully closing and the valve operator was proptly readjusted. ~

No problem was acted with the sealing function of AH-V1B.

The valve pair tested satisfactarily after the adjustments with leakage below the administrative limit set by the surveillance procedure (a pressure In drop of 0.24 psi over a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> perled vs. an allowable of 0.40 psi).

addition, the updated tatal leakage for Reactor Building valves and penetra-tians is less than the technical specification limit (35,254 scem vs. an alicwable 111,899 secm).

1476 156 3

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5 Page 2 i Mr. J.P. O'Reilly i June 17.1975 As fmrestigation wfit be conductM to determiae the reason that AR-VIA required adjustment te seat properly.

Based en the results of the investigation appropriate corrective actiorr will be taken.

Very truly yourb J.G. flerhein Station Superintendent JSE/dra f

1476 157 7

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