ML20085E608

LER ER-76-003:on 760209,eddy Current Testing Revealed Greater than Expected Steam Generator Tube Degradation.Cause Probably Associated W/Previous Steam Generator Water Treatment Program

ML20085E608
Person / Time
Site:	Palisades
Issue date:	02/24/1976
From:	Bixel D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20085E610	List: ML20085E608 ML20085E613
References
LER-ER-76-003, LER-ER-76-3, NUDOCS 8308150433
Download: ML20085E608 (2)

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EVENT REPORT pv Palisades CONTROL BLCCK:l l l l/ l l l (PLEASE PRINT ALL REGUutED INFORMATION) 1 6

% AME UCENSE NUMBER PE TY

'O l MlI l P l Al Ll 1l l 0 l 0l-l0 l 0 l 0l 0l 0l-l 0 l 0l lh l1 l1 l1 l1l l 0l1 l 7 89 14 15 25 28 30 31 32 nEponT asPoar

• TYPE SOUACE DOCKET NUMBER EVENT OATE REPORT DATE

@ CONT l l l LT.J l.L l l 01 sl 01-1012 l 51 si lol21 ol ol 716l l 01 212 lh 171 61 7 8 57 58 59 60 81 08 89 74 75 80 EVENT OESCRIPTION 35 l Preliminary analysis of eddy current results obtained while eddy current testing l 7 89 80 SE lof the Palisaaes steam generators indicates that some steam generator tubes may havel 7 89 80 g l degraded more than expected. Further information on these results of the testing l 7 89 80 DE lvill be presented in accordance with the Technical Specifications requirement l 7 89 80 g lfor the augmented Inservice Inspection Program for steam generators (ER-76-03). l 7 89 m 80 DE CODE COMPONENT CODE vcLATON me Ic 1 7I b.J Ial mi ElxI cln i Ltti I cI al9 Io I I Ni

'7 89 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION DE l The cause of the degradation is probably associated with the previous SG water l 7 89 80

$E !trentr!ent Drocre.**.  !

7 89 80 EE I I STA  % POWER QTHER STATUS 06 VERY OtSCOVERY DESCAPTON 7 8 9 d 10 l0l0l0l12 l13 NA l @ l NA l 44 45 48 80 AELEA EO OF EL ASE AMOUNT OF ACTMTV LOCATON OF RELEASE BE L2J LzJ l NA l l NA 7 8 9 10 11 44 45 l.

80 PERSONNEL EXPOSURES NUMBEA TYPE CESCAPTON 8101 olo I 7 89 11 LzJ 12 l

13 NA l 80-PERSONNEL INJURIES NUMBER DESCRPTON EE l 010l0 l l NA l 7 89 11 12 80 PROBABLE CONSEQUEN;ES 3 I Degradation of the reactor coolant uressure boundary. I 7 89 80 LOSS OR OAMAGE TO FAClUTY TYPE DESCAPTON G2 l zj l NA l 7 89 10 80 PUBLICITY 36 i NA l 7 89 80 ADDITIONAL FACTCRS I!E89I i 80 8I 7 89 i 80 8308150433 760224 PDR ADOCK 05000255 S PDR

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Mr James G. Keppler -

Office' of Inspection Enforcement Region III US Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 DOCKET 50-255, LICENSE DPR-20 PALISADES PLANT, ER-76-03, s STEAM GENERATORS Attached is a reportable occurrence which relates to the Palisades Plant and has been classified as possible degradation of steam geners. tor tubes above that which was expected. The degradation was determined as a part of the steam generator inspection.

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David A. Bixel Assistant Nuclear Licensing Administrator 1

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