05000263/LER-1980-021-03, /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: |
| References | |
| LER-80-021-03L, LER-80-21-3L, NUDOCS 8006200472 | |
| Download: ML112900751 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| 2631980021R03 - NRC Website | |
text
REGULATORY IJRMATION DISTRIBUTION SYS*
(RIDS)
ACCESSION NBR:8006200472 DOC.DATE: 80/06/12 NOTARIZED: NO FACIL:50-263 Monticello Nuclear Generating Plant, Northern States AUTHNAME AUTHOR AFFILIATION OVERLID,TW.
Northern States Power Co, RECIPNAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director DOCKET #
05000263 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 ID CODE/NAML CTION:
BC /PIOL/7VI)*05 NTERNAL: A/D RAD PROT A/D TECHNOLOGY AUX SYS BR CONT SYS BR EMERG PREP HANAUER,S, I&E 09 MPA 11 OP EX EVAL BR 01 4i;;i ERAC BR COPIES LTTR ENCL 4
4 1
1 1
1 1
1 2
3 3
1 1
1 RECIPIENT ID CODE/NAME COPIES LTTR ENCL A/D REACT SYS 1
AEOD 10 CHEM ENG BR I
EISENHUTD, I
EQUIP QUAL BR 1
I&C SYS BR 1
JORDANE,/IE 1
NRC PDR 02 1
OR ASSESS BR 1
QA BR 1
SIT ANAL BR 1
TERA:DOUG MAY 1
1 10 1'
1 1
1 1
1 1
1 1
1 03 1
1
'JUN 2 3 TOTAL NUMBER OF COPIES REQUIRED:
LTTR XTERNAL:
16 LPDR 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:
t-Director, MIPC, USNRC (3)
MPCA Attn:
J W Ferman
- - over 8006200
NRC FORM 366 (7-77) 7 8
CON'T 7
8 78 08-2 57 7
U. S. NUCLEAR REGULATORY COMMISSION health or safety.
9 80 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 9
(LI@
lAJ@ L I&
I RIE IL lA lY IX I 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 L@z LzJ Lo 10 1llol LNJ23 L.@ Li A 11 10 19 I 33 34 35 36 37 40 41 42 43 44 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. 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@ 1 0 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 1oL IRI NA 1
8 9
11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION8 I 0 1 0o 0 11 NA 1
8 9
11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
LT IIZI NA 7
8 9
10 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
LICENSEE EVENT REPORT CONTROL BLOCK:
I (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
IM IN IM IN IP Ill on -
00IolololOi 0-1010I01411111 l(~
- 1) 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 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 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 event No previous similar events. No effect on public I
1,l JA~t.~L'.~.
t--I
!r, NI C FOR [0I (7.1) 7 8
CON'T 7
8 0T41 7
9 iM 366 U. SCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK:
0 I(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
IM IN IM IN IP 1i l lo In 1-1 ol 01 ol 0 01 -l ol 0o
( 4 11 11 1 (@)
9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 REPORT
_L11 0 l5 l0 10 01 21 6L 3 01 O 51 11 51 81 0 &
01 6 1 11 21 81 0 ORCE I
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 I demonstrated daily during event.
No previous similar events.
No effect on public l health or safety.
YSM SYSTEM
,CAUSE
CAUSE
COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE Lc:M J0 LAJ@ L liOI RIE IL lA jY IX 1 H4 j
[Zj 7
8 9
10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO rEVENT YEAR REPORT NO.
CODE TYPE NO.
10 RE PORT NUJMBER II 10~ 1a2J11 1 0L1 s W~ -
Li L.21 22 23 24 26 27 28 29 30 31 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 WI Z_
Wi 10 10 1111 LW L
IA 11 0 19 1 33 34 35 36 37 40 41 42 43 44 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 1 J I 0 1 5 15 I9 NA I B (.'I Surveillance Test 8
9 10 12 13 44 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 o
1 z1I NA I.
8 9
11 12 13 80 PERSONNEL INJURIES NUMBER
DESCRIPTION
EE 01 01 0 1 NA 7.
8 9
11 12 80 LOSS OF OR DAMAGE TO FACI LITY TYPE
DESCRIPTION
ID I z I NA I
7 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 so "N o 7 POEam 612) 2()I-';1g1