05000263/LER-1980-013-01, /01T-0:on 800309,during Refueling Operations,Rod Withdrawn Block Not Received When Refueling Bridge Traversed Core.Caused by Actuating Arm Out of Adjustment.Components Readjusted & Interlocks Tested Prior to Refueling
| ML112900665 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 03/21/1980 |
| From: | Myrabo A Northern States Power Co |
| To: | NRC/OI/RGN-III/FO |
| Shared Package | |
| ML112900666 | List: |
| References | |
| LER-80-013-01T, LER-80-13-1T, NUDOCS 8003240564 | |
| Download: ML112900665 (4) | |
| Event date: | |
|---|---|
| Report date: | |
| 2631980013R01 - NRC Website | |
text
REGULATORY oORMATION DISTRIBUTION SY-*M (RIDS)
ACCESSION NBR:8003240564 DOC,DATE: 80/03/21 NOTARIZED: NO DOCKET #
FACIL:50-263 Monticello Nuclear Generating Plant, Northern States 05000263 AUTHNAME AUTHOR AFFILIATION MYRABO,A,L, Northern States Power Co.
RECIP.NAME RECIPIENT AFFILIATION MYRA8OAL.
Region 3, Chicago, Office of the Director SUBJECT: LER 80-013/01Tw0:on 800309,during refueling operationsrod withdrawn block not received when refueling bridge traversed core.Caused by actuating arm out of adjustmentComponents readjusted & interlocks tested prior to,refueling.
DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR.1 ENCL 4 SIZE:._J J TITLE: Incident Reports NOTES: ----------------------------.---------------------- -------------
RECIPIENT C
ID CODE/NAME L
ACTION:
05 BC INTERNAL:
EG FIL 09 14 TA/EDO 16 EES 18 PLANT SYS BR 20 AD PLANT SYS 23 ENGR BR 25 PWR SYS BR 27 OPERA LIC BR 29 AUX SYS BR AEOD HANAUERrS, JORDANE,/IE OPIES TTR ENCL 4
4 1
2 1
1 1
1 1
1 1
1 1
1 1
RECIPIENT ID CODE/NAME 02 NRC PDR 11 MPA 15 NOVAK/KNIEL 17 AD FOR ENGR 19 I&C SYS BR 22 REAC SAFT BR 24 KREGER 26 AD/SITE ANAL 28 ACDENT ANLYS AD/ORP-DOR DOUG MAY-TERA IRELAND,R,.
COPIES LTTR ENCL 1
3 1
1 1
1 1
1 1
1 3
1 3
3 1
1 1
1 1
1 1
1 3
EXTERNAL:
03 LPDR 29 ACRS 1
16 1
16 04 NSIC TOTAL NUMBER OF COPIES REQUIRED: LTTR 1
1 52 ENCL 52
1" 0
4SIP 0
NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA 55401 March 21, 1980 Mr J G Keppler Office of Inspection & Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen E11yn, IL 60137
Dear Mr Keppler:
MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Refueling Rod Block Interlock Failure The Licensee Event Report for this occurrence is reproduced on the back of this letter. Enclosed are three copies.
This event is reported 'in accordance with Technical Specification 6.7.B.1.g. in that the condition (limit switch out of adjustment) required refueling operations to be stopped in accordance with Technical Specification 3.10.A.
Yours very truly, N"
L 01 M Ma ager of Nuclear Support Services LOM/JAG/ak cc: &..Director, IE, USNRC (40)
Director, MIPC, USNRC (3)
MPCA Attn:
J W Ferman
- - over 75 0
NRC FORM 366 (7-77) 8 CON'T 7
8 7
8 7
8 S1 U. S. NUCLEAR ItEGULATO;IY COMMISSION L
9 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE LF.LDJ@ LW1O@ LA]
I1 INI SIT IR jU 19 L1 LzI@
9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR REPORT NO.
CODE TYPE NO.
8[
REPORTSI O
R RN 1C 1131 EUTAO U
R RVS 21 22 23 24 26 27 28 29 30 31 32 A"TION FUTURE EFFECT SHUTDOWN ATTACHMENT NPAD-4 PRIME COMP.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM bUB.
SUPPLIER MANUFACTURER IE1 F
z 1 Z JO 10 l0 l0 l1 l N 1Nj J 1j LG 10 8 10 l 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 2
I Refueling operations were immediately stopped. Investigation revealed that the actu-I Iating arm of the limit.switch ( which opens when the bridge is over the core) was out I of adjustment, preventing the switch from operating properly. The components were I
readjusted & interlocks tested prior to resuming refueling. Modifications of the j
i components are being considered.
7 8
9 FACILITY STATUS
% POWER OTHER STATUS LH H 1
j0 10 10 1(51 NA I
7 8
9 10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY
[
D[6 1 Lz[J0l NA 1
7 8
9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE.
DESCRIPTION
7 8
9 11 12 13 PERSONNEL INJURIES NUMBER
DESCRIPTION
EEo 1 010 @1 7
8 9
11 12 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
E LJ@I 7
8 9
10 PUBLICITY ISSUED
DESCRIPTION
ILNJ1 7
8 9
10 METHO METHO DISCOV 4A 45 NAME OF PREPARER 80 0 OF ERY DISCOVERY DESCRIPTION (2i) Operator observation 46 80 LOCATION OF RELEASE 1
NA l
45 80 NA I
80 NA I
80 NA 80 NRC USE ONLY NA I
I l Il l I l I l l l l 68 69 80 PH 612/295-5151 x-266 80032,A n5
/
0 A. IggbMyrabo w
LICENSEE EVENT REPORT CONTROL BLOCK: [
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
IMIN I MINI P1 110101 01 -ll 01 ol olol-l ol ol@ 4 1 1111 11 0 LLJ0 9
LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 REPORT j@1 RCEL 05 1 01 0 1 01 21 61 3()
01 31 01 91 81 01@1 0 3l1 2
1 8l 1 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (3 lAt 0605, it was discovered that a rod withdrawal block was not received when the refi1-i ling bridge traversed the core during refueling operations. Technical Specification I
3.10.A requires the refueling interlocks to be operable during core alterations, InterF Ilocks had successfully been tested at 0400 the previous day. Records for that period confirmed that no control rods had been moved while fuel was moved. The event had no jeffect on the public health or safety. One previous occurrence. AO-75-02.
00
NFAC FO rJi F
CONT 7
8 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 0
I D LJ Ll@j I I1 NI SIT IR jU 1 LsJS Lj@
7 8
9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LE/OfEVENT YEAR REPORT NO.
CODE TYPE NO.
REPORT 8
0 1
1 31 L---
1 01 1I LTJI 1---_
E N 21 22 23 24 26 27 28 29 30 31 32 A!TION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB.
SUPPLIER MANUFACTURER 0 0E F I Z]
(
l0 0 00 6
3Nj 0
I [NN j IG 10 18 1010 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 0 Refueling operations were immediately stopped.
Investigation revealed that the actu-I lating arm of the limit switch ( which opens when the bridge is over the core) was out I 2 of adjustment, preventing the switch from operating properly.
The components were j
1 readjusted & interlocks tested prior to resuming refueling.
Modifications of the I
4 components are being considered.
7 8
9 80 FACILITY METHOD OF STATUS
% POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION 2
1 5 LJ 10 l10 1 0 1 5 NA I L J(3I Operator observation 7
B 9
10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 1G O W lNA
_0 EI L J@
JgD I
@A NA I
7 8
9 10 11 44 so PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
1010 0 Z(a NA 1
7 8
9 11 12 13 80 PERSONNEL INJURIES NUMBER
DESCRIPTION
0 1 0 0 1 NA 1
7 8
9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
IDI Z 11 I
7 8
9 10 80 PUBLICITY NRC USE ONLY ISSUED
DESCRIPTION
7 N6 1A I
69l ll 7
8 9
10 68 69 80o A. L. Myrabo NAME OF PREPARER 0
PHONE: 612/295-5151 x-266 PHNE J--
RM 366 U. S. NUCLEAR IREUULAOU'iY COMMISSION C
CE NS3E E EVE N T R EPO0R T CONTROL BLOCK:
O '
PLEASE PRINT OR TYPE AL L REQUIRED INFORMATION)
MAIN I MINI P il I
0 01
- - 0 0, I0 10 c0 cI -1014 1 11 1O1O111OLLJ0 9
LICENSEE CODE 14 iS LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 6s REPORT
_L 01 510101 01 21 61 3)1 013101918 1 0 01312,1j.1.1D1j0o(
SOUR CE CLI\\_________________
60 61 DOCKET NUMBER 6F 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES jAt 0605, it was discovered that a rod withdrawal block was not received when the refuel -1 ling bridge traversed the core during refueling oDerations.
Technical Specification I
3.10.A requires the refueling interlocks to be operable during core alterations.
Interi jocks had successfully been tested at 0400 the previous day.
Records for that period ponfirmed tt no c os 1
h-ad been mo.-ved~ w ihile ful was moved.
The event had no i
ieffect on the public health or safety. One previous occurrence. AO-75-02.
H-I 80