05000272/LER-1982-081, Supplemental LER 82-081/01X-1:on 821104,16 1,000-kip Steam Generator Snubbers Found Out of Spec on Bleed Test & Six Snubbers Failed Acceleration Test.Caused by Flattened Piston Seal Rubber Matl Due to Aging.Seals Rebuilt

Supplemental LER 82-081/01X-1:on 821104,16 1,000-kip Steam Generator Snubbers Found Out of Spec on Bleed Test & Six Snubbers Failed Acceleration Test.Caused by Flattened Piston Seal Rubber Matl Due to Aging.Seals Rebuilt

ML20071D778
Person / Time
Site:	Salem
Issue date:	03/03/1983
From:	Frahm R Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20071D659	List: 05000272/LER-1982-081, Supplemental LER 82-081/01X-1:on 821104,16 1,000-kip Steam Generator Snubbers Found Out of Spec on Bleed Test & Six Snubbers Failed Acceleration Test.Caused by Flattened Piston Seal Rubber Matl Due to Aging.Seals Rebuilt
References
LER-82-081-01X, LER-82-81-1X, NUDOCS 8303140568
Download: ML20071D778 (1)

LER-2082-081, Supplemental LER 82-081/01X-1:on 821104,16 1,000-kip Steam Generator Snubbers Found Out of Spec on Bleed Test & Six Snubbers Failed Acceleration Test.Caused by Flattened Piston Seal Rubber Matl Due to Aging.Seals Rebuilt

Event date:
Report date:
2722082081R00 - NRC Website

text

Cf3D(E23CD U. S. NUCLE A7 REIULATO.Y COMMISSION (7 77)

, . LICENSEE EVENT REPORT CONTROL BLOCX: l l l l l l l (PLEASE PRINT OR TYPE ALL RE7UIRED INFZ.MATIONI 1 6 lo lil8 IN 7 9 laLICENCEE is ! clCODESil l@15l 0101 -l LICENSE 14 0101010101NUMBER -l 0125 ol@l4LICENSE 26 l1111ilil@l TYPE JO I

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7 8 60 61 DOCKET NUMBER 68 61. 74 75 REPOPT DATE PO EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES 01o

@ lDuring routine surveillance testing from October 29 to November 11, 1982, the sixteen j g g ,3 ,

. 1000 kip steam generator snubbers were found to be out of specification on the bleed g g g i, , ; test required by the Technical Specifications. Six snubbers also friled the acceleratqon

[gy3g; test. Engineeringevaluationdemonstratedthat,inadesignbasisevent,nofailureog l 0 l6 l l the Reactor Coolant System piping would occur. The snubber degradation invcived the ,

g y 7 g ; potential failure of compor.ents which would prevent performance of safety equipment ,

,g,g, ;as analyzed in the FSAR, in accordance with Technical Specification 6.9.1.8e.  ;

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]glRl2l3l6g 43 44 47 CAUSE DERRIPTION AND CORRECTIVE ACTIONS h g l Investigation of the problems revealed that the snubber piston seal rubber material l 1 i lhad flattened due to aging. The snubbers had been assembled in 1974; shelf life l l m 7] lof the seals is now estimated to be 7 years. The seals were rebuilt using original l l

l l 3 l l parts and the snubbers were satisfactorily tested. Seals with improved materials l

! l1 g ,are presently being investigated. l 7 8 9 80 TA S "wPOWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION

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ACTIVITY CGt TENT RELEASED OF RELEASE AVOUNT OF ACTIVITY LOCATION OF RELEASE l1 l6l h hl N/A l l N/A l PERSONNEL EXPOS ES NUV3ER DESCRIPTION l

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0 l 0 l 0 lhlTYPEZlhl N/A l PERSONNEL INJU IES NUMBER DESCRIPTION R l 809 l 0 l O lhl 7 11 12 N/A go l

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, 8 9 o 83031405gB y y h PUBLICITY PDR ADOC PDR ISSUED DESCRIPTION O $ e E Lt.L181 7 8 9 10 N/A I i iiiiiiiiiiiIi 68 69 80 E

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