ML18219B524

06/02/1978 Letter Licensee Event Report

ML18219B524
Person / Time
Site:	Cook
Issue date:	06/02/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	James Keppler NRC/IE, NRC/RGN-III
References
LER 1978-015-03L, LER 1978-029-03L
Download: ML18219B524 (6)

Text

Wpj+jgg REGULATORY INFORhtATION DISTRIBUTION SYSTEN (RIDS)

DISTRIBUTION FOR INCONING MATERIAL 50-316 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 06/02/78 NRC IN 8c NI PWR DATE RCVD: 06/08/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-316/78-029) ON 05/11/78 CONCERNING THE HAIN TURBINE STOP VALVE "D" CLOSURE LIMIT SWITCH BECANE INOPERABLE... W/ATT LER 78-015.

PLANT NAME: COOK UNIT 2 REVIEWER INITIAL: XJM INITIAL:PQ 'ISTRIBUTOR DISTRIBUTION OF THIS NATERIAL IS AS FOLLOWS 4++4+4++<+<++++<++

hlOTES:

i. SEND 3 COPIES OF ALL NATERIAL TO ISE ED REEVES-1 CY ALL NATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002>

FOR ACTION: BR CHIEF LWR02 BC++W/4 ENCL INTERNAL: REG FILE++W/EN NRC PDR++W/ENCL I 5 C S '~

44W/2 ENCL NOVAK/CHECK4+W/ENCL

~4W/ENCL MIPC44W/3 ENCL EMERGENCY PLAN BR>+W/ENCL EEB~~W/ENCL AD FOR ENG%>W/ENCL PLANT SYSTEMS BR++W/ENCL HANAUER++W/ENCL AD FOR PLANT SYSTENS++W/EhlCL AD FOR OPER TECH>+W/ENCL REACTOR SAFETY BR>>W/ENCL ENGINEERING BR++W/ENCL VOLLNER/BUNCH++W/ENCL KREGER/J. COLL INS++W/ENCL POWER SYS BR++W/ENCL K SEYFR IT/IE++W/ENCL EXTERNAL: LPDR~S ST. JOSEPH'I++W/ENCL T I C.~~~ W/ENCL NSIC++W/ENCL ACRS CAT B4+W/16 ENCL GPPZES NOT SUB lITTED PER PZGULATORY GUIDE 10.1 DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 78160 330 SIZE: iP+1P+1P THE END

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yg~g INDIANA 5 MICHIGANPOSER COIPPAJVY DONALD C. COOK NUCLEAR PLANT ~VJ P.O. Box 458, Bridgman, Michigan 49106 (D. 3 I

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g June 2, 1978 g (n~.)

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:

Pursuant to the requirements of the Appendix A Technical Specifications the following reports are submitted:

RO 78-015/03L-1 RO 78-029/03L-0 Sincerely, D.Y. Shaller Plant Manager

/bab cc: J.E. Dolan R.M. Jurgensen R.F. Kroeger R. Kilburn R.J. Vollen BPI K.R. Baker RO:III R.C. Callen MPSC P.M. Steketee, Esq.

R. Malsh, Esq.

G. Charnoff, Esq.

G. Olson J.M. Hennigan PNSRC J.F. Stietzel Dir., IE (30 copies)

Dir., MIPC (3 copies) 78l600330 PP'

MR010RM 39I NUCLEAR REGULATORY COMMISSION '

I7-77)

LICENSEE EVENT REPORT CONTROL BLOCK:

6 Q1 {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

M I D D C 2 Q20 0 00 00 00 00 0Q34 I I I IQ4L L IQs 7 8 UCENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T

~01 SOURCE MLQB P P 3 1 6 Q7 0 5 1 1 7 8 QB 0 6 0 2 7 S Qe 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUEPICES Q10 DURING NORMAL OPERATION, ON MAY ll AND 14, 1978, THE MAIN TURBINE STOP VALVE "D" CLOSURE LIMIT SWITCH BECAME INOPERABLE. THIS SWITCH PROVIDES

~O3 A TRIP SIGNAL LISTED IN T~ S ~ TABLE 3 '-1 ITEM 18 ', IN BOTH OCCASIONS THE APPLICABLE ACTION REQUIREMENTS WERE FULFILLED.

~OS

~OB

~OB 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENTCOOE SUBCOOE SUBCODE

~o9 7 8

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~IA 9 10 QII ~EQ12 11

~BQ13 12 13 I N 6 T R 0 18 QI" ~SQ19 19

~Z 20 Q'9 SEQUENTIAL OCCURRENCE REPORT REVISION LERI'RO EVENT YEAR REPOIIT NO. CODE TYPE NO.

Qii 999092 ~78 21 22 i=I 23 ~ 24I p~(9 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMEhtT NPR&4 PRIME CohIP. COMPONENT TAKEN ACTION ON PLANT I IETHOD HOURS Q22 SUBMITTEO FORM SUB. SUPPLIER hlANUFACTURER

'BQIs 33

~ZQI9 34

~ZQ20 35

~ZQ21 36 , 37 0 0 0 0 40

~YQ23 41

~Y.

42 Q24 ~gQ29 43 44 I 9 47 Q29

~ CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o NA

~14 7 8 9 9

FACILITY STATUS

~EQis ~06

% POWER 9 Q29

=

NA OTHER STATUS ~

~3O METHOD OF DISCOVERY

~QSI OISCOVFRY DESCRIPTION Q32 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RCLEASE AMOUNTOF ACTIVITY~3S LOCATION OF RELEASF QSB

~Z Q33 Z Q34 NA NA 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 8

~00 9

0 11 Q~ZQ3' 12 13 80 PERSONNEL INJURIES NULIBER DESCRIPTIONQ41

~OO O Qio NA 7 8 9 11 12 80 LOSS OF OR DAL'IAGE To FACILITY TYPE DESCRIPTION Q43 O Z Q2 NA 7 8 9 10 80 PUBLICITY O

ISSUED

~NQ44 DESCRIPTION Q NA NRC USE ONLY 44 7 8 9 10 68 69 80 o NAME QF PREPARER Jack Rischling 616-465-5901 0 a

NRC FNFIM~~o l7 77) "UPDATWERORT PREVIOUS REPORT ISSUED'25/78" LICENSEE EVENT REPORT COE'4TROL BLOCK IPLEASE PRINT OR TYPE ALL REQUIRED INFORMATION),

I 6

~O 7 8 9 I! I D LICENSEE CODE C C 2 14 Qz0 15 0 0 0 0 0 0 LICENSE NUAllBER 0 0 0 OQ3 2S 26 4 1 1 LICENSE TYPE 1 1 30 QE~QE57 CAT 58 CON'T

~O REPQRT IL I~S 0 5 0 0 0 3 1'6 Q70 Qs 0 6 0 2 7 8 Qe SOURCE 7 8 60 61 DOCKET NUEREIBE R 68 69 EVEIVT DATE ~ 74 75 REPORT DATE 80 EVENT OESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING THE INITIAL POI(ER TESTING PROGRAM, ROD POSITION INDICATION (RPI) FOR ROD

~O3 0-12 MAS FOUND TO BE IN EXCESS OF THE + 12 STEP LIMIT (T.S. 3.1.3.2) THREE TIMES

~O4 ON MARCH 22 and 23, 'l978. ALSO ON MAR(H 23, RPI FOR RODS H-2, P-8, F-'10 AND K-10

~OS MERE FOUND TO EXCEED THE T. S- LIblIT.

~O7

~OS 7 8 9 80 SYSTEM CAUSE CAUSE CORVIP. VALVE CODE CODE SUBCOOE CO'IPONENT CODE SUBCOOE SUBCOOE 7 6 9

~IE 10 Qii 11 E Qi2 ~EQ43 12 13 I N S T R U 18 Qi4 ~YQEE 19

~Z 20 Qg SEQUENTIAL OCCURREiNCE REPORT REVISION

~

~

LERIRQ EVENT YEAR REPORT NO. CODE TYPE NO.

Qiz RgipRP ACTIOiV FUTURE TAKEN ACTION L778J 21 22 EFFECT 23 SHUTDOWN

~01 24 5

26

~m 27

~03, 28 ATTEAC74hIENT

'9 iNPRD 4

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. 30 PRILIE COMP.

31 ~

~l 32 CohIPONENT

~ ON PLANT METHOD HOURS +22 SUBMITTED FORh1 SUB. SUPPLIER MANUFACTURER

~EQ48 ~ZQEE ~ZQzp ~ZQ24 0 0 0 0 Y Qzz ~NQ24 ~NQ28 . tl 1 . 2 0 Qzg 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 8 INVESTIGATION REVEALEO THAT OF THE THREE EVENTS CONCERNING RPI FOR D-12,THO INVOLVED ADJUSTING THE SPAN ON THE CONDITIONING MODULE. APPARENTLY, ON THE REMAINING TMO EVENTS RPI HAD RETURNED TO MITHIN THE 12 STEP SPECIFICATION PRIOR TO INITIATING ANY REPAIR 3 ACTION.

4 7 8 9 80

~lg FACILITY STATUS

~BQ28 ~00 IGPOWER 7 Qzg OTHER STATUS NA

~

~SO METHOD QF DISCOVERY

~AQEE OPERATOR OBSERVATION DISCOVERY DESCRIPTION Q32 7 8 9 10 12 13 44 45 80 6

ACTIVITY CONTENT RELEASED OF RELEASE

~z Q33 ~ZQ34 Ah10UNT OF ACTIVITY NA

~ NA LOCATION OF RELEASE Q 7 8 9 - 10 11 44 45 80 PERSOiJNEL EXPOSURES NUMBER TYPE DESCRIPTION QSB 7 ~00 0 Q37 ~Q38 NA 7 8 9 11 12 I3 PERSONAE L INJURIES 7 8 9 11 12 80 LOSS QF OR OAAIAGE TO FACILITY TvPs DESCRIPTION Q43

~ZQ42 NA 8 9 10 80 o

PUBLICITY ISSL'Ef D DESCRIPTION ~ NA NRC USE ONLY 44 48

'8 9 10 68 69 80 8

ER t

NAI'AE'F PREPARER Jack Rischling 616-465-5901 0 IL 0