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

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 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 pri-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

• _ ..;:,;

• LICENSEE EVENT REPORT ~

CONTROL BLOCK: I I. I I I [PLEABE PA~T ALL lllEGUUllED INFORMATION) 1 6 LICENSE EVENT LICENSE NUMBER TYPE TYPE lolol-lolololol ol~lolol I 41 i J ii 1 l 1 I I oh I 15 25 26 30 31 32 REPORT REPORT TYl>E. SOURCE OOCKl;T NUMBER EVENT DATE REPORT DATE (i;iJ1jcoN'T I *I I l..l..I LL.J IoI sI ol-1 o I2 I 5 I 5I Io I 3 I 2 I a. 11 I 674I I oI 75 sI ol 6 I 1 I 6 I 80 7 B 57 58 59 *so 61 BB 69 EVENT DESCRIPTION lo(2f IDuring the Palisades local leak rate testing, the test on penetration #46 showed I 7 8 9 80 lol3f I.leakage above acceptable limits (about lll liters/min). The leakage was associated I 7 B 9 BO lol41 jwith one of two in series valves. The second valve performed satisfactorily. I 7 B 9 BO lol5f !Affected parts replaced. (ER-76-011) I 7 B 9 BO lolsl 7 B 9 PRME BO SYSTEM CAUSE COMPONENT COMPONENT COOE CODE COMPONENT CODE SUPPLER MANUFACTURER VIOLATION

@0 Isl DI W I vI Al LI v I EI xi l.!.J I Ml l I 21 01 L!.J 7 B 9 10 11 12 17 43 44 47 40 CAUSE DESCRIPTION 7

lolBI l The valve (CV-1101) is a 4" globe valve with Tef':j_on soft seats.

B 9 .

Inspection dis-BO I

lolsl I closed that the seats were worn from use (normal wear). The valve is a 150 psi ASA I r.

7 B 9 BO 8 9 lrated valve made of carbon steel. Model 38-2057i. and is air operated.

. BO I

FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION

[iE] Uil lo I o I o I I......*-~NA:.::....__ ___,I L1lJ NA 7 8 9 10 12 13 44 45 46 BO FORM OF ACTIVITv CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE IIE) L!J Llj ._I_ _ _N_A_ _ ___.I NA 7 8 9 10 11 44 45 BO PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~I ol ol g L~l NA 7 8 9 *11 12 13 BO PERS"ONNEL INJURIES NUMBER DESCRIPTION

~I 01 0101 NA 7 8 9 . 11 12 80 PROBABLE CONSEQUENCES .

~ I None. Redundant valve operated properly. I 7 B 9 BO LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION EfilB 9liJ 7 10 NA 80 PUBLICITY fil?.lB 9 7

NA 80

~ ADDITIONAL FACTORS NA

~9 80 80