ML19343C026
| ML19343C026 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/12/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, SQRD-50-328-81, NUDOCS 8102180514 | |
| Download: ML19343C026 (2) | |
Text
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TINN ESSEE V LLE'. A UT H C :l"Y c, s - t..c 3 3 ::: n.3 : t 400 Chestnut Street Tower II February 12, 1981 i
4 SQRD-50-328/81-14 ft f
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- C v.hianaps M Mr. James,, O'Reilly, Director k6 comai#
- s Office of spection and I'.: fm coment U.S. Nuclear egulatory Commission g
4 Region II - Su te 3100 N
101 Marietta St et Atlanta, Georgia 30303
Dear Mr. O'Reilly:
SECUOYAH NUCLEAR PLANT UNIT 2 - LEAKAGE 0/ METAL BELLOWS ON PRL4ARY CONTAINMElff PENETRATION - SQRD-50-328/81 FINAL REPORT The subject deficiency was initially reported to NRC-CIE Inspector F. S. Cantrell on January 13, 1981, in accordance with 10 CFR 50.55(e) as NCR 2519 Enclosed is our final report.
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If you have any questions, please get in touch with D. L. Lambert at FTS 857-2581.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Regulation and Safety Enclosure
/
cc: Mr.VictorStello, Director (Enolasure)V Office of Inspection and Enforcement U.S. Nuclear Regulatory Commiission Ashington, DC 20555 ga/f 5'/
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i ENCLOSURE SEGUOYAH NUCLEAR PLANT UNIT 2 LEAKAGE OF METAL BELLOWS ON PRIMARY CONTAINMENT PENETRATION SQRD-50-328/81-14 10 CFR 50.55(e)
FINAL REPORT Descriotion of Deficiency The leakage rate of a metal bgliows on primary contain=ent penetration X-30, Azi=uth 291, elevation 697 feet, was found to be 60.4 standard cubic feet per hour when it should have been airtight.
This leak rate test was perfor=ed by pressurizing through a test connection betwaan the two single-ply bellows and measuring the rate a
of pressure lost. The test connection is used for test purposes only and is not qualified to =aintain contain=ent integrity. The leakage was determined to be on the internal bellows because no leakage or defects were evident on the outer one. This was verified by a localized leak test inside the penetration assembly. Leak rate tests for local penc', rations as outlined by 10CFR50, Appendix J, are designed to periodically check the '.ntegrity of the centainment pressure boundary. This piping penitration assembly, which includes the bellows, was tested by Tube Turns Division, member AL Metals Group, Allegheny Ludlum Resources, Incorporated, Louisville, Kentucky,.
'Eifoie" shipment and found to be airtight. The weld that attaches the bellows to the penetration assembly was believed to have been damaged by inadvertent grinding. Apparently, when attempting to grind l
the root on the adjacent weld, the weld on the bellows was ground by mistake.
Safety Implications 1
Had this leakage gone undetected, and had the outer bellows or test
' connection leaked, radioactivity in excess of levels claimed in the plant safety analysis could have been released to the atmosphere' during a LOCA. This could have adversely affected the safety of the plant by jeopardizing the health and safety of plant personnel and the public.
Corrective Action Due to difficulty of gaining access for repairing the weld on the internal bellows, a similar bellows of a greater diameter will be welded concentric with'the original bellows. This will ensure containment pressure integrity and testing ability. Modifications should be complete by April 1, 1981.
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