ML20027B276

LER 82-088/03L-0:on 820804,valve Stem Spun Freely Beyond Full Open Valve Position During Manual Opening of Suppression Pool,Suction Supply Valve RHR 2-E11-F004B, Pump B,Loop B.Caused by Stem Fracture 6 Inches from Gate

ML20027B276
Person / Time
Site:	Brunswick
Issue date:	08/31/1982
From:	Pastva M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20027B272	List: ML20027B271 ML20027B276
References
LER-82-088-03L-02, LER-82-88-3L-2, NUDOCS 8209160603
Download: ML20027B276 (1)

Text

NRC FORM 366 U. S. NUCLE AR REGULATORY COMMISSION (7 77)

LICENSEE EVENT REPORT

s. CONTROL BLOCX: l 1

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lh (PLE ASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo lt]8 lN 7 9 lCLICENSEE l Bl CODE El Pl 2 l@l0 l0 l- l0 LICENSE 14 15 l0 l0NUMBER l0 l0 l- l0 l0 l@l 25 264 l 1l LICENSE1l 1l TYPE 1l@l Ju l

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S$R$60 l L @l Ol SIDOCKET 61 0l -l Ol 3l 2l 684lhl690l 8lEVENT NUMBER 0l4 l8 l2 l@l 0l 8REPORT DATE 74 75 l 3l DATEll 8 l 2 80l@

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l 012 l lWhile manually opening the suppression pool suction supply valve to B pump of B loop l

g ;3; l RHR, 2-Ell-F004B, the valve stem spun freely beyond the full open valve position. Thel

og,y l unit was in cold shutdown at the time of this discovery. This event did not affect thd

,o g ; health and safety of the public. l I

LoJ 6_) I Io I7I I I io,g, , Technical Specifications 3.5.3.2, 6.9.1.9b l C DE CODE SUBCO E COMPONENT CODE SU8 COD'E SU E lO19l l Cl Fl@ Wh I X lh l V l A l L l V l E l X lh (F_jh (_pj h 18 19 20 7 8 9 10 11 12 13 SEQUENTIAL OCCUR R E NCE REPORT REVISION LER RO EVENT YEAR REPORT NO. CODE TYPE N O.

O agg 18l21 22 l-j 23 101 al al 24 26 I/l 27 10131 28 29 LL_J 30 L-J 31 10 1 32

_ 21 T K N A T ON ON PL NT ET HOURS SB IT FOR1 8. SUPPL MA FACTURER lAl@lXl@ [Z_j@ (_Z_jh 3

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(_)dh l43 N lh I A l 3 l 9 l1 47 lh 33 34 35 36 40 42 44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l i l 0 l l Disassembly of the valve revealed a complete fracture of the stem annroximnte 6 inchon I

,, ,,,;from the valve gate. A new valve stem was installed and the valve was satisfactorily I

,,, g cycled and returned to service. Following the completion of a metallurgical analysis I

, 3 gof the failed valve stem a supplement will be submitted outlining any required further l g

corrective actions regarding this event. l 7 8 9 80 l ST S  % POWER OTHER STATUS IS O RY OlSCOVERY DESCRIPTION l1 l5l h l0l0l0l@l NA l l A l@l Operator Surveillance l

, ACTIVI TY CO TENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE

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[Z_j @ [Ql 10 11 NA 44 l l 45 NA 80 l

s PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

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• PERSONNd'iNa'iES

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NA l e 7 i a 8 9 10l DER l0l@l 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION

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! 7 8 9 9209160603 820031 80 PUBLICITY PDR ADOCK 05000324 NRC USE ONLY

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M. J. Pastva, Jr. PHONE:

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