ML112900751

LER 80-021/03L-0:on 800515,during Normal Startup,Reactor Core Isolation Cooling Control Power Fuse Opened.Caused by Shorted Relay Coil in Circuit Due to Ac Relay Inadvertently Installed by Maint Personnel.Relay Replaced

ML112900751
Person / Time
Site:	Monticello
Issue date:	06/12/1980
From:	Overlid T Northern States Power Co
To:	NRC/OI/RGN-III/FO
Shared Package
ML112900752	List: ML112900751 ML19318A387
References
LER-80-021-03L, LER-80-21-3L, NUDOCS 8006200472
Download: ML112900751 (4)

Text

REGULATORY IJRMATION DISTRIBUTION SYS* (RIDS)

ACCESSION NBR:8006200472 DOC.DATE: 80/06/12 NOTARIZED: NO DOCKET #

FACIL:50-263 Monticello Nuclear Generating Plant, Northern States 05000263 AUTHNAME AUTHOR AFFILIATION OVERLID,TW. Northern States Power Co, RECIPNAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director

SUBJECT:

LER 80-021/03L-0:on 800515,durinq normal startuppreactor core isolation cooling control power fuse openedCaused by shorted relay coil in circuit due to ac relay inadvertently installed by maint personnel.Relay replaced.

DISTRIBUTION CODE: A0028 COPIES RECEIVED:LTR J ENCL SIZE:

TITLE: Incident Reports NOTES: - - ----- ---- --------

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAML LTTR ENCL ID CODE/NAME LTTR ENCL CTION: BC /PIOL/7VI)*05 4 4 NTERNAL: A/D RAD PROT 1 A/D REACT SYS 1 1 A/D TECHNOLOGY 1 AEOD 10 10 AUX SYS BR 1 CHEM ENG BR I 1' CONT SYS BR 1 EISENHUTD, I 1 EMERG PREP 1 EQUIP QUAL BR 1 1 HANAUER,S, 1 I&C SYS BR 1 1 I&E 09 2 JORDANE,/IE 1 1 MPA 11 3 NRC PDR 02 1 1 OP EX EVAL BR 3 OR ASSESS BR 1 1 1 QA BR 1 1 01 1 SIT ANAL BR 1 1 4i;;i ERAC BR 1 TERA:DOUG MAY 1 1 XTERNAL: ACRS 16 16 LPDR 03 1 1 NSIC 04 1

'JUN 2 3 TOTAL NUMBER OF COPIES REQUIRED: LTTR 60 ENCI 60

NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 June 12, 1980 Mr J G Keppler Office of Inspection & Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137

Dear Mr Keppler:

MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 RCIC Control Problem The Licensee Event Report for this occurrence is reproduced on the back of this letter. Enclosed are three copies.

This event is reported in compliance with Technical Specification 6.7.B.2.b. in that this condition led to operation in a degraded mode permitted by limiting condition for operation Specification 3.5.F.2.

Y urs very truly, M yer, PE an er of Nuclear Support Services LOM/JAG/ak cc: Director, IE, USNRC 30 )

t-Director, MIPC, USNRC (3)

MPCA Attn: J W Ferman

-over 8006200

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7-77)

LICENSEE EVENT REPORT CONTROL BLOCK: I (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 IMINIM INIPIll14 on - 00IolololOi 0-1010I01411111 25 26 LICENSE TYPE l(~

30 1) 57 CAT 58 7 8 9 LICENSEE CODE 15 LICENSE NUMBER CON'T REPORT L] 10 15 10 10 l 01 21 61 3 (2)1 01 51 11 5 81 01I1 016 1 1 21 81 010 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES IDuring normal startup while performing surveillance test, the RCIC control power fuse Openedcausingthe RCIC system to be inoperative (T.S.3.5.F.2), HPCI system operability A + +A AnTil A1ivinci I 1,l event No previous similar events.

JA~t.~L'.~. t--I No effect on public 78 08-2 health or safety.

57 7 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 9 (LI@ lAJ@ L I& I RIE IL lA lY IXI HjJ [Zj 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO FEVENTYEAR REPORT NO. CODE TYPE NO.

21 22 23 240. 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 2 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER UAJ6 33 34

@ L@z 35 LzJ 36 Lo 10 1llol40 LNJ23 37 41 L.@

42 Li 43

@ A 44 11 10 19 47I CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Fuse opened due to a shorted relay coil in the RCIC DC control power circuit. An AC relay had inadvertently been installed by maintenance personnel during design change installation. Relay replaced with proper DC relay and system tested satisfactorily. I Maintenance personnel instructed in necessity of using only the exact specified I 1 part in all applications.

89 80 FACILITY 30 METHOD OF STATUS %POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION SLCj@ 10 1 5 l 5 NA [jI Surveillance Test

8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE EE Lz.1 I NA I NA I 7 a 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION &

EE1 o 1 8 9 11 12 IRI1oLNA13 80 PERSONNEL INJURIES NUMBER DESCRIPTION8 I 9 0 1 0o 011 1112 NA 80 1 8 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION LT IIZI 7 8 9 10 NA 80 PUBLICITY NRC USE ONLY ISSUED UESCRIPTION

[2]0 INA 11111 II 11 7 8 9 10 68 69 80 NAME OF PR PER PH (612) 29-sisi soo62 00 m

!r, NI C FOR iM 366 U. SCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (7 [0I

.1) CONTROL BLOCK: I(PLEASE0 PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 l lo In 1- 1 olLICENSE 01 ol0 01 -l ol0o ( 26 4 11 1 (@)

IM IN IM IN IP 1i NUMBER 25 11 LICENSE TYPE 30 57 CAT 58 7 8 9 LICENSEE CODE 14 15 CON'T REPORT _L11 0 l5 l0 10 01 21 6L 3 01 O 51 11 51 81 0 & 01 6 111 21 81 0 ORCEI 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES I During normal startup while performing surveillance test, the RCIC control power fuse ppenedcausingthe RCIC system to be inoperative (T.S.3.5.F.2). HPCI system operability 0T41 I demonstrated daily during event. No previous similar events. No effect on public l health or safety.

7 9 YSM SYSTEM ,CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE Lc:M J0 LAJ@ L RIE IL lA liOI jY IX 1 18 19 H4j [Zj 20 7 8 9 10 11 12 13 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO rEVENT YEAR REPORT NO. CODE TYPE NO.

10 REPORT NUJMBER II L.21 22 23 10~1a2J11 26 24 27 128 0L1s29 30 W~-

31 Li 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED FORM SUb. SUPPLIER MANUFACTURER UU@LHi 33 34 WI 35 Z_ 36 10 10 37 Wi1111 40 41

@ LW 42 L

43 IA 11 44 0 19 1 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Fuse opened due to a shorted relay coil in the RCIC DC control power circuit. An AC relay had inadvertently been installed by maintenance personnel during design change installation. Relay replaced with proper DC relay and system tested satisfactorily.

Maintenance personnel instructed in necessity of using only the exact specified I 1 part in all applications.

9 80 FACILITY o METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 8 9 1 J I 0 1 5 15 I9 10 12 13 NA 44 I B (.'I Surveillance Test 45 46 80 PCTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE RELz..E O .J NA I - I NA 7 8 9 10 11 44 45 811 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Em lo 8 9 o 11 1z1I 12 13 NA 80 I.

PERSONNEL INJURIES NUMBER DESCRIPTION EE 01 01 0 1 NA 80 7 . 8 9 11 12 LOSS OF OR DAMAGE TO FACI LITY TYPE DESCRIPTION 7

ID Iz I NA I 8 9 10 . 8 PUBLICITY NRC USE ONLY ISSUED UESrRIPTION 72N j (NAI I I l l Il I I 7 8 9 10 68 69 so8 NNAME OF PR RER T. W. Overlid 612) 2()I-';1g1 so"No 7 POEam