ML20031C140

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RO 10-74:on 740426,during Biannual Containment Leak Rate Test,Newly Installed Inner Supply Valve CV4097 Leaked at Sphere Side Flange.Caused by Insufficient Tightening of Flange Bolting.Bolts Tightened & Leakage Stopped
ML20031C140
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 05/06/1974
From: Sewell R
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
US ATOMIC ENERGY COMMISSION (AEC)
References
RO-10-74, NUDOCS 8110060575
Download: ML20031C140 (3)


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}D014 Mr. John F. O' Leary, Director Re: Docket 50-155 Directorate of Licensing License DPR-6 United States Atomic Ener67 Cor: mission Big Rock Point Plant Washington, DC 20545 l

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Dear Mr. O' Leary:

Attached is a copy of Abnomal Occurrence Report 10-74 for the Big Rock Point Plant.

1 Yours ve.ry truly, a

T Ralph B. Sevell (Signed)

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ABNORMAL OCCURRENCE REPORP Big Rock Point Plant 1.

Report No A0-10 Docket 50-151 1007Y 2a.

Report Date - Aay 6,1974, 2b.

Occurrence Date - April 26, 197k.

3 Facility - Big Rock Point Plant.

4.

Identificatics - Ventilation Valve CV 4097 Flange Leak.

5 Conditions Prior to Occurrence - Refuelin/; Shutdown, 6.

Description - During the bi-annual containment leak rate test, the newly installed inner supply valve leaked at the sphere side flange. It was discovered by inspection after the centainment leak rate test data indicated excessive leakage at the 13 psig pressure. The leakage air was sampled and founl to be essenti-ally at background radioactivity level.

7 Designation of Apparent Cause - The flange boltinc was not tightened sufficiently on initial installation earlier in this refueling outsge period.

8.

Analysis of Occurrence - The flange leak rate was measured and found to be less than two cubic feet per minute. This represents an amount greater than allevable for the leak rate test conditicr..

However, the defective conditions had existed only since the valve was installed during this refueling outage. Since the air expelled during the test was at essentially background radiation levels, it is felt that no undue hazard existed at the facility.

9 Corrective Action - The flange bolts were tightened and the leakege was stopped while the sphere remained pressurized to approc.inately 13 psig for the leak rate test. The contaicnent leak rate e st var continued cnd completed satisfactorily.

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10. Failure Data - Not Applicable.

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