05000316/LER-1980-035-03, Rod Position Indication for Rod N-9 Did Not Respond Properly While Pulling Shutdown Control Rods in Preparation for Going Critical.Connector on Top of Rod Position Detector Assembly Appeared Stepped on

Rod Position Indication for Rod N-9 Did Not Respond Properly While Pulling Shutdown Control Rods in Preparation for Going Critical.Connector on Top of Rod Position Detector Assembly Appeared Stepped on

ML17331A653
Person / Time
Site:	Cook
Issue date:	02/20/1981
From:	Rischling J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17331A654	List: 05000316/LER-1980-035, Forwards Updated LER 80-035/03X-1 05000316/LER-1980-035-03, Rod Position Indication for Rod N-9 Did Not Respond Properly While Pulling Shutdown Control Rods in Preparation for Going Critical.Connector on Top of Rod Position Detector Assembly Appeared Stepped on
References
LER-80-035-03X, LER-80-35-3X, NUDOCS 8102270813
Download: ML17331A653 (8)

LER-1980-035, Rod Position Indication for Rod N-9 Did Not Respond Properly While Pulling Shutdown Control Rods in Preparation for Going Critical.Connector on Top of Rod Position Detector Assembly Appeared Stepped on

Event date:
Report date:
3161980035R03 - NRC Website

text

.'%k REGULATO INFORMATION DISTRIBUTION STEM (RIDS)

SUBJECT:

Updated LER 80.-035/03X"1:on 801206~rod position indication for rod N

9 did not respond properly while pulling shutdown control rods in preparation of going critical ~ Connector on top of rod position detector assemhly appeared stepped on, COPIES RECEIVED:LTR ENCL ~

SIZE DISTRIBUTION CODE e A002S TITLE: Incident Reports ACCESSION NBR;8102270813 DOC e DATE! 81/02/20 NOTARIZED; NO DOCKET FACIL:50-316 Donald C,

Cook Nuclear Power Plant< Unit 2~ Indiana 8

05000316 AUTH BYNAME AUTHOR AFFILIATION RISCHLING~J, Indiana L Michigan Electric Co, RECIP ~ NAMEl RECIPIENT AFFILIATION Region 3i Chicago~ Office of the Director NOTES:Send 3 copies of all material to I8E ~

05000316 REC IP IENT ID CODE/NAME'CTION VARGAr 8 ~

04 INTERNAL: A/D COMPLSTRU06 II A/D NATL 8

QU08 A/D PLANT SYS10 A/D SFTY ASSE12 AEOD AUX SYS BR 15 CONT'YS BR 17 DIRiDIV OF LIC DIRiHUM FAC S21 EFF TR SYS BR23 GEOSCIENCES

?6 IaE; 05 LI C GUID BR 30 MECH ENG BR 33 NRC PDR 02 OR ASSESS BR 35 BR39 01 S

Y PROG EVA42 SYS INTERAC 845 COPIES LTTR ENCL 3

3 1-1 1

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RECIPIENT ID CODE/NAME A/D ENV TECH 07 A/D OP REACT009 A/D RAD PROT 11 ACC EVAL BR 14 ASLBP/J ~ HARD CHEM ENG BR 16 CORE PERF BR 18 DIR p ENGINEERI20 DIRg SYS INTEG22 EQUIP QUAL BR25 ILC SYS BR 29 JORDANzE ~ /IE MATL ENG BR 32 MPA OP EX EVAL BR34 POWER SYS'R 36 REACT SYS BR 40 REL L RISK A 41 STRUCT ENG BR44 COPIES LTTR ENCL 1

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EXTERNAL; ACRS NSIC 46 05 16 16 1

1 LPDR 03 TERA:DOUG. MAY TOTAL NUMBER OF COPIES REQUIRED:

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4 (j me@4:an lectrla INDIANA& MICHIGANELECTRIC COMPANY DONALDC. COOK NUCLEAR PLANT P.O. Box 468, Bridgman, Michigan 49106 (616) 465-6901 February 20, 1981 Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 Operating License DPR-74 Docket No. 50-316

Dear Mr. Keppler:

Attached please find Licensee Event Report RO 80-035/03X-1 which was revised to add a more definitive Cause Description and Corrective Action.

Sincerely, D.V. Shaller Plant Manager

/bab cc:

J.E.

Dolan R.S. Hunter R.W. Jurgensen R.F. Kroeger R.W. Kilburn E.

Swanson/N.

DuBry RO:III R.C. Callen MPSC G. Charnoff, Esq.

J.M. Hennigan W. Lavallee EPRI PNSRC J.F. Stietzel E.L. Townley

'ir.,

IE (30 copies)

Dir., MIPC (3 copies)

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NRC FORM 366 (7.77)

CONTROL BLOCK UPDATE REPORT -'REVIOQPgjg Dgj) 01)02/81 Qi (PLEASE PRINT OR TYPE ALI. REQUIRED INFORMATION)

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CON'T

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9 LICENSEE CODE 14 15 LICENSE NUMBER RE 0

~06 07 60 61 DOCKET NUMBER 68 69 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 010 03 Q4~

QE 25 26 LICENSE TYPE 30 57 CAT 58 QB 0

2 2

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09 EVENT DATE 74 75 REPORT DATE 80

~O3 INDICATION FOR ROD N-9 DID NOT RESPOND PROPERLY.

THE REACTOR TRIP BREAKERS WERE

~O4 OPENED.

THIS EVENT WAS NON-CONSERVATIVE IN RESPECT TO TECHNICAL SPEC IFICATI

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80 SYSTEM

CAUSE

CAUSE COMP VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LERgRO EVENT YEAR REPORT NO.

CODE TYPE NO.

Q17 REPORT g~

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~l 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ PRIME COMP.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.

SUPPLIER MANUFACTURER

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~QEE CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 027 o

THE PROBLEM WAS TRACED TO A CONNECTOR ON TOP OF THE ROD POSITION DETECTOR ASSEMBLY.

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~11 A SPARE CABLE WAS SUBSTITUTED FOR THE ORIGINAL AND ROD POSITION INDICATION FOR ROD N-9 WAS DECLARED OPERABLE.

SEE SUPPLEMENT FOR ADDITIONAL INFORMATION.

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METHOD OF DISCOVERY F031 45 46 45 NAME OF PREPARER JaCk RiSChling 4

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9 FACILITY

STATUS,

% POWER OTHER STATUS 5

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10 12 13 44 ACTIVITY CONTENT RELEASED OF RElEASE AMOUNTOF ACTIVITY EKI LzJ 0 ~03 7

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10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 ZDQ LoaoLOJSL~JS 7

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11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION~41

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9 11 12 LOSS OF OR DAMAGETO FACILITY 43 TYPE

DESCRIPTION

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10 PUBLICITY ISSUED DESCRIPTION~

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10 DISCOVERY DESCRIPTION Q32 LOCATIONOF RELEASE Q NRC USE ONLY 68 69 61 6-465-5901 80 80 80 80 80 80

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v' SUPPLEMENT TO LER 50-316/80-35 CAUSE DESCRIPTION THE DEFECTIVE CONNECTOR APPEARED TO HAVE BEEN STEPPED ON.

IT SHOULD BE POINTED OUT THAT THE AREA ABOVE THE REACTOR HEAD IS A VERY DIFFICULT AREA TO WORK IN.

SUPPORT CABLES ARE STRUNG OVER THE REACTOR HEAD TO FORM A GRID WHICH SUPPORTS INSTRUMENTATION AND POWER CABLES.

DURING EXTENSIVE JOBS, PLANKS ARE PLACED ON THE SUPPORT CABLES TO PREVENT ANY DAMAGE AS REPORTED BY THIS LER.

AT TIMES, IT IS NOT PRACTICABLE TO USE THE ADDITIONAL SUPPORTS ON THE GRID AREA WHICH INCREASES THE POSSIBILITY OF SUCH AN EVENT.

TO PREVENT REOCCURRENCE, A MEMO WAS SENT TO ALL DEPARTMENT HEADS TO REVIEW THIS EVENT WITH THEIR PERSONNEL WHO MAY,WORK IN THE AREA OF THE REACTOR HEAD.

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