ML18346A251

LER 1981-002-00 for Palisades Nuclear Plant, Inadequate Mounting of DC Distribution Panel

ML18346A251
Person / Time
Site:	Palisades
Issue date:	01/26/1981
From:	Hoffman D Consumers Power Co
To:	James Keppler NRC/RGN-III
References
LER 1981-002-00
Download: ML18346A251 (2)

Text

consumers

• Power company General Offices: 212 West Michigan Avenue, Jackson, Michigan 49201 * (517) 788-0550 January 26, l98l Mr James G Keppler Office of Inspection and Enforcement Region III U S Nuclear Regulatory Commission 199 Roosevelt Road Glen Ellyn, IL 60121 DOCKET 50-255 - DPR PALISADES PLANT -

LICENSEE EVENT REPORT 81-002 - INADEQUATE MOUNTING OF DC DISTRIBUTION PANEL On the reverse side is LER 81-002 which is reportable under Technical Specifi-cations 6.9.2.B(2).

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David P Hoffinan Nuclear Licensing Administrator CC Director, Office of Nuclear Reactor Regulation Director, Office of Inspection and Enforcement NRC Resident Inspector, Palisades Plant JAN 2* 8 J981

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NRC FORM 366 (7*77)

• PALIS ADES PLANT U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROLBLOCK: ~l~..__.....___.~_.___._~1(2) (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

~ IM I r I Pl A I LI l 101 o I ol - lo Io I o I ol o I - Io Io 101 4 11 I l I JJ l l©I I 10 7 B 9 LICENSEE CODE 14 ,5 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T CITLl ~:~~~ LlJ©I o 1s Io I o Io I 2 I 5 Is l(?)I. o 111 o 18 18 11 l©I o I ll 2 I 618 I 1 IG) 7 B 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE BO EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

!During post installation review of fire protection modifications, it was

[]JI] I determined t:ti.at: 125 volt DC distribution panel D2lA was not adequately

• • *  ;. ! ~*.ii~*

• _. *.

[QE) 1mounted in tern:is Of meeting seismic restraint criteria. The redundant panef-ITTIJ 1D-llA wa~*. properly mourite~. The. loads supplied by the panel (1-2 Diesel

[]ID 1Geri. and 2400V Bus lD) were declared inoperable; repairs were initiated &

~ I completed within time required by LCO of TS 3. 7. 2c. No threat to public

I !health. or safety existed. I 7 B 9 BO

.SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE IIITJ IEICI@ ~@ ~@ ISIUIPIOIRITI@ ~@) ~@

7 B 9 10 11 12 13 18 19 20

. SEQUENTIAL OCCURRENCE REPORT REVISION LERIRO CVENT YEAR REPORT NO. CODE TYPE NO.

@ REPORT NUMBER l 8 I 11 l=J I o I 01 2 I l ......-1 Io 13 I Ill l=I l£J 21 22 23 24 26 27 28 29 JO 31 32 ACTION FUTURE EFFECT SHUTDOWN r:;:;.. ATTACHMENT NPRD-4 PRIME COMP. COMPONENT

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TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FOAM ~us. SUPPLIER MANUFACTURER lli.J@Lz.J@

33 34 W@

35 W

36 101010101 37 40 lli.J@

41 lli.J@

42

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43 IN 13 15 15 44 47 I \

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

[III] !The seismically qualified panel was mounted on a field fabricated frame IIID lwhich was insufficiently braced. The apparent. cause was incorrect

[I]}] 1engineering judgement by A/E during project design. To satisfy seismic

[j]JJ !restraint criteria, frame was modified by addition of braces.

CiJil 7 8 9 BO FACILITY (.;Q\ METHOD OF {.;':;\

STATUS  % POWER OTHER STATUS ~ DISCOVERY DISCOVERY DESCRIPTION ~

QE W@ I ol9 '8 l@,_l_.w...A_ _ _ _ -J LQJ@I Notification by AE 8 9 10 12 13 44  % ~ ~

ACTIVITY CONTENT ~

RELEASED OF RELEASE AMOUNT OF ACTIVITY~ LOCATION OF RELEASE @)

~ LzJ @) &J@,_I----'N=A-=--_ _ ____. NA 7 8 9 10 11 44 45 BO PERSONNEL EXPOSURES ~

NUMBER r::=;.. TYPE DESCRIPTION

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7 B 9 Io I o Io 11l0lzJ@!-::--l.L!:~--------------------___J 12 13 BO PERSONNEL INJURIES f,;";\

NUMBER DESCAIPTION6 Eli]

7 B I 9 a I o Io 11I@ ~12~~~~_..........._~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~....JBO LOSS o< OR DAMAGE TO FACILITY t4:j\

TYPE DESCRIPTION ~

[iEJ W@ A 7 8 9 10 BO PUBLICITY C\

ISSUED(,;;\ DESCRIPTION~ NRC USE ONLY I2I9J Ur..J~,__~~~~~.IU.l....~~~~~~~~~~~~~~~.....1 8 9 10 68 I I 69 II I I I I I I I I I 80