ML18352A346

Transmittal of Licensee Event Report (LER) ER-76-011 Containment Isolation Valve

ML18352A346
Person / Time
Site:	Palisades
Issue date:	05/07/1976
From:	Bixel D Consumers Power Co
To:	James Keppler NRC/IE, NRC/RGN-III
References
Download: ML18352A346 (2)

Text

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• consumers Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201

• Area Code 517 788-0550 May 7, .1976 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-76-0ll CONTAINMENT ISOLATION VALVE Attached is a Licensee Event Report which relates to the Palisades Plant. This event was originally thought to be nonreportable since containment integrity was not required at the time the problem was observed and a second isolation valve performed satisfactorily.

Later review disclosed that it may be reportable as "abnormal degradation discovered in the mary containment." Such an interpretation must conclude that degradation of one of two in series valves designed to isolate containment is intended to be reported under the prompt notification requirements.

David A. Bixel Assistant Nuclear Licensing Administrator CC: R. A. Purple, USNRC

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• LICENSEE EVENT REPORT CONTROL BLOCK: I 1 I . I I I [PLEABE ALL lllEGUUllED INFORMATION) 6 LICENSE NUMBER lolol-lolololol 15 25 REPORT REPORT LICENSE TYPE I 41 i J ii 1 l 1 I 26 30 EVENT DATE EVENT TYPE I oh I 31 32 REPORT DATE (i;iJ1jcoN'T I *I I 7 B 57 58 TYl>E. SOURCE l..l..I LL.J OOCKl;T NUMBER I o I s I ol-1 o I 2 I 5 I 5 I Io I 3 I 2 I a 11 I 6 I I o I s I ol 6 I 1 I 6 I 59 *so 61 BB 69 . 74 75 80 EVENT DESCRIPTION lo(2f I During the Palisades 7 8 9 local leak rate testing, the test on penetration

1. 46 showed I 80 lol3f I.leakage above acceptable limits (about lll liters/min).

The leakage was associated I 7 B 9 lol41 jwith one of two in series valves. The second valve performed satisfactorily. 7 B 9 lol5f !Affected parts replaced. (ER-76-011) 7 B 9 lolsl 7 B 9 SYSTEM COOE @0 Isl DI CAUSE CODE COMPONENT CODE W I v I Al LI v I EI xi 7 B 9 10 11 12 17 CAUSE DESCRIPTION PRME COMPONENT SUPPLER l.!.J 43 COMPONENT MANUFACTURER I Ml l I 21 01 44 47 VIOLATION L!.J 40 lolBI l The valve (CV-1101) is a 4" globe valve with Tef':j_on soft seats. Inspection dis-7 B 9 . lolsl I closed that the seats were worn from use (normal wear). The valve is a 150 psi 7 B 9 r. lrated valve made of carbon steel. Model 38-2057i.

and is air operated. 8 9 . FACILITY METHOD OF STATUS % POWER OTHER STATUS DISCOVERY

[iE] Uil lo I o I o I I ......

• _ ___,I L1lJ 7 8 9 10 12 13 44 45 FORM OF ACTIVITv CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY IIE) L!J Llj ._I ___ N_A ___ __.I 7 8 9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION ol ol g 7 8 9 *11 12 13 PERS"ONNEL INJURIES NUMBER DESCRIPTION 01 0101 7 8 9 . 11 12 PROBABLE CONSEQUENCES . I None. Redundant valve operated properly. 7 B 9 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Efil liJ 7 B 9 10 PUBLICITY fil?.l 7 B 9 ADDITIONAL FACTORS 45 46 NA NA NA NA NA DISCOVERY DESCRIPTION NA LOCATION OF RELEASE NA BO I BO I BO BO I BO ASA I BO I BO BO BO BO 80 I BO 80 80 80 80