05000331/LER-1980-044-03, /03X-1:on 800824,rod Block Monitor B Began Indicating Downscale Causing Continuous Rod Withdrawal Block.Caused by Improperly Seated Pin Connector at Rod Select Matrix Panel.Connector Seated
| ML112410937 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/28/1981 |
| From: | Rager M IES Utilities, (Formerly Iowa Electric Light & Power Co) |
| To: | NRC/OI/RGN-III/FO |
| Shared Package | |
| ML112410938 | List: |
| References | |
| LER-80-044-03X, LER-80-44-3X, NUDOCS 8105040298 | |
| Download: ML112410937 (3) | |
| Event date: | |
|---|---|
| Report date: | |
| 3311980044R03 - NRC Website | |
text
REGULATOR 6 NFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR:8105040298 DOCDATE: 81/04/28 NOTARIZED: NO DOCKET #
FACIL:50-331 Duane Arnold Energy Center, Iowa Electric Light & Pow 05000331 AUTHONAMEI AUTHOR AFFILIATION RAGERMS.
Iowa Electric Light & Power Co.
RECIPNAME RECIPIENT AFFILIATION.
Region 3, Chicago, Office of the Director SUBJECT: LER 80-044/03X-on 800824,rod block monitor 8 began indicating downscale causing continuous rod withdrawal block.Caused oy improperly seated pin connector at rod select matrix panel,Connector seated.
DISTRIBUTION CODE: A00aS COPIES RECEIVED:LTR 4'NCL SIZE:.,/
TITLE: Incident-Reports NOTES:
RECIPIENT ID CODE/NAME ACTION:
IPPOLITOT. 04 INTERNAL; A/D COMP&STRU06 A/D MATL & QU08 A/D PLANT SYS1O.
A/D SFTY ASSEl2 AEOD ASLBP/J.HARD CHEM ENG BR 16 CORE PERF BR 16 DIRHUM FAC S21, EFF TR SYS BR23 GEOSCIENCES 26' I&E 05 LIC GUID BR
- 30.
MECH ENG BR 33:
OR ASSESS BR 35 ASd BR39 G
01 SFTY PROG EVA42 EXTERNAL: ACRS NSIC 46 05; COPIES LTTR ENCL 3
3 16 1
1 1
1 1
3 1
1 1I 1
1I 1
'1 1
1 1
1
'I1 1
16 1
RECIPIENT ID CODE/NAME COPIES LTTR ENCL A/D ENV TECH 07 A/D OP REACTOO9 A/D RAD PROT 11 ACC EVAL'BR 14 AEOD/DMU AUX SYS BR 15 CONT SYS BR 17 DIR,ENGINEERI20 DIR,SYS INTEG22 EQUIP DUAL BR25 I&C SYS BR 29 JORDANE,/IE MATL ENG BR 32 NRC POR 02 POWER SYS BR 36 REACT SYS BR 40 REL & RISK A 41 STRUCT ENG 8R44 LPDR 03 1
1 MAY 0 5 1981 fr/f TOTAL NUMBER OF COPIES REQUIRED: LTTR 61 ENCL 61
Iowa Electric Light and Pbwer Company April 28, 1981 DAEC-81-269 Mr. James G. Keppler, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission -
Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Licensee Event Report No.80-044 UPDATE REPORT:
(30 day)
Previous Report Date 9-23-80 File:
A-118a
Dear Mr. Keppler:
In accordance with Appendix A to Operating License DPR-49, Technical Specifications and Bases for Duane Arnold-Energy Center and Regulatory Guide 10.1, please find attacfed a copy of the subject Licensee Event Report.
(Total of 3 copies transmitted).
Very truly yours, Daniel L. Mineck Chief Engineer Duane Arnold Energy Center DLM/MSR/pl Docket 50-331 attachment cc:
Director, Office of Inspection and Enforcement (30)
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Director, Management Information and Program Control (3)
U.. S. Nuclear Regulatory Commission Washington, D. C.
20555 U. S. Nuclear Regulatory Commission co Document Management Branch Washington, D. C.
20555 NRC Resident Inspector -
DAEC MAY -
,4 1981 Duane Arnold Enermv Center
- PO. BoX 351
- Cedar Rpids, Iowa =406
- 319/851-5611
NRC POR (7.")
.4 7
8 CON'T 7
8 02 71 7
.8 0901 7
8 SYSTEM
CAUSE
CAUSE Comp.
VALVE CODE COO SUSCOO COMPONENT COOS SU8CODe SUSCOD Ir 1 10 [EJ@
L-.,
0 i
N T
I I
T I R l ul LES I
D 9
10 st 12 13 la 19 20 SEQUENTIAL OCCURRENCE REPORT
~.LER/RO EVENT YEAR REPORT NO.
coos Type RE PORTW LLAA W
W i x
@ UMER 1 a.1 1 01 41 4I 10 1 3' 1 IJ
,-d r21 22 23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SNUTOOWN ATTACHMENT NPRO-4 PRIME COMP.
TAKEN ACTION ON PLANT MET400 HOURS 22 SUBMITTED FORM usu.
SUPPLIER
&J LZIJ@
L@
Il..JO 00 0 10 1 LJ LNS L.N@
1 33 34 35 38 A
40 41 42 CO43S CAUSE DESCRIPTION AND CORRECTIVE ACTIONS0 REVISION NO.
L1J 32 COMPONENT MANUFACTUER G 10 18 10 I I4 47 1
1 Cause was an improperly seatpd pin r 1 Pin il hin yed tn havie Ivihrated Inn T12 I rs were seated and panel tested sati 1TI I ed to service within the hour. GE co 14 I en installed to preliide woamirrence FACILITY STATUS
% POWER OTH0R STATUS 1
L J@ 1 0 1 7 1 4131 NA I
7 8
9 10 12 11 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY EE16 LzJ @ LJ1 NA I
7 8
9 to 11 44
- PERSONNEL EXPOSURES nNUMSER TYPE
DESCRIPTION
TI inin (I JL Zj71I NA 7
8 9
11 12 13 PERSONNEL INJURIES NUMBER OESCRIPT1ON oTI ILLo a11 NA 7
8 9
11 12 LOSS OF OR DAMAGE TO FACILITY TYPE OESCRIPTION 1 I1e1 NA 7
8 9
10 PUB3LICITY ISSUED
DESCRIPTION
No S NA 7
8 9
10 NAME OF PREPARER Matthew S. Rager nnnc~rtnr at RndSelect Matriy PaneL se ounr period of time Pin connecto sfactorily. Channel B RBI was return mnponents. Locking connectors have be of this type 80 METHOO OF DISCOVERY DISCOVERY DESCRIPTION [A 101 Operator Observation 45 46 80 LOCATION OF RELEASE I
NA 45 80 so 80 80 NRC USE ONLY 68 69 So.
PHONE:
319-851-5611 0
M 36 S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT TE REPORT: Previous ort Date 9-23-80 CONTROL BLOCK:
J JlQ(PLEASE PRINT OR TY'i ALL REQUIRED INFORMATION)
I A ID JA IC 1(
0 0l01
- - 1 oIoloIoIo-o-
0314 11 1 1 L111lel 0
9 LICENSEE CO0E 14 LICENSE NUMBER S
26 LICENSE TYPE 30 57 C S8 SOURCE LLGI15 10 10 1013131 1 101812 141 81 Oj@1 0 141 21181 IS 1 1 w6 61 DOCKET NUMBER 68 as EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES I During power ascension. the "R" Rod Rinrk Monitor (RRM) hphan indicating I
1 downscale for any rod selected causing a continuous rod withdrawal block.
1 Rod withdrawals were continued with the "A" RRM operable and the "R" RRM I
I bypassed. Tech. Spec. Table 3.2-C allows operation with one RBM bypassed I
1 for up to 7 days. In accordance with T.S.3.3.R.5 rod withdrawal was blnc I
I ked when a limiting control rod pattern reached with one RRI channel ino I Derable. There have been two previous oncrrences RO 0-36. 79-2)
I 9
80