ML17317B431

Forwards LER 79-037/03L-0 & Revised LER 79-034/03L-0, Changing Rept Number to 79-036/03L-0

ML17317B431
Person / Time
Site:	Cook
Issue date:	08/08/1979
From:	Shaller D INDIANA MICHIGAN POWER CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17317B432	List: ML17317B431 ML17317B433 ML17317B434
References
NUDOCS 7908140650
Download: ML17317B431 (5)

Text

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~erlcen yste c SUKL00$JblleldfZ DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 August 8, 1979 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-58 Docket No. 50-315

Dear Mr. Keppler:

Pursuant to the requirements of the Appendix A Technical Specifications the following report/s are submitted:

RO 79-037/03L-O.

In addition to the above report, please find attached a revised copy of RO 79-034/03L-0 which was inadvertently given the same number as a pre-viously submitted report. This report should be number as RO 79-036/03L-0 and is reflected in the attached revised LER.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan PNSP.C R.W. Jurgensen J.F. Stietzel R.F. Kroeger Dir., IE (30 copies)

R. Kilburn Dir., MIPC (3 copies)

R.J. Vollen BPI R.E. Masse RO:III R.C. Callen MPSC P.W. Steketee, Esq.

R. Walsh, Esq.

G- Charnoff, Esq.

G. Olson J.M. Hennigan

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION CENSEE EVENT REPORT CONTROL BLOCK:

I 6 Q (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~4

~os 7 8 9 M I D LICENSEE CODE C C 1QE 14 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 DQ 25 26 4 1 LICENSE TYPE 30 O~QE57 CAT 58 CON'T

~01 " ~LQR 0 5 0 0 0 3 1 5 QT 0 7 0 9 7 9 Qs 0 8 0 8 7 9 Qs 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES ~10 WHI LE I N MODE TWO CONDUCTING CONTROLMOD WORTH TESTI'NG IT WAS DISCOVERED THAT THE INDICATED POSITION OF CONTROL BANK C RODS C-3,C-13, N-13, N-3 AND H-6 EXCEEDED

~Do 44T HE T W E LV E S T E P L I M I T I MP 0 S E D BY T. S. 3. 1 .3.2. I S I M LAR 0 C C U R R E N C E S I N C LU D E

~OS 050-315/76-13,44,54; 315/77-27,28,33,34; 315/78-04,07,38,40,46; 315/79-01,14,23,

~OB 24; 050-315/78-07,08,22,31,41,48,64,75,84,93, AND 316/79-14.

~OS 80 7 . 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

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Q17 LERIRP REPoRT LU9 21 22 U

23 L0037 24 26 I K+I 27

~03 28 29 LiJ 30 PRIME COMP.

31 32 COMPONENT ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDQ TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~EQER ~Z Q19 ~2 Q20 ~Z QEE 0 0 0 1I N Q22 ~NQ24 N Q28 W 1 2 0 QEE 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 ACTUAL ROD POSITION TWAS DETERMINED T L 9

SECONDARY COIL VOLTAGE MEASUREMENTS. THE EVENT CAUSE WAS TRACED TO EACH RESPECTIVE RODS SIGNAL CONDITIONI'NG MODULE WHICH HAD DRIFTED. FOLLOWING ADJUSTMENT ALL INDICATORS FUNCTIONED PROPERLY. AN ENGINEERING REVIEW IS IN PROGRESS TO DETERMINE THE CAUSE OF THIS RECURRI'NG PROBLEM.

7 8 9 80 FACILITY STATUS  % POWER OTHER STATUS Q DZG8 &BQ28 ~00 1 Q NA 44

~AQSI OPERATIONAL EVENT 80 7 9 10 12 13 45 46 ACTIVI'TY CONTENT RELEASED OF RELEASE AMOUNT@ ACTIVITYQSS LOCATION OF RELEASE Q I:I:I '33 7 8 9

~Q34 10 44 45 NA 80 PERSONNEL EXPOSURES

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13 80 PERSONNEL INJURIES

~II'"'II'"0 Qs'"'" ""Q NA 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY Q43

~~Q42 NA 7 8 9 10 80 PUBLICITY NRC USE ONLY 7 8 9 10 68 69 80 48 616-465-5901 0 NAME OF PREPARER T. P. Beilman PHONE:

4 NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION

'(7-77)

CENSEE EVENT REPORT CONTROL BLOCK 1 6 01 N

(PLERSE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 8 9 M I D C LICENSEE CODE C 1 14 Q2 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 25 QS 26 4 1 1 1 LICENSE TYPE 1

30 04~02 57 CAT 58 CON'T

~01 7 8 SRURSCE MQ 60 61 0

DOCKET NUMBER 68 QSO 69 7 0 EVENT DATE 9 7 9 74 Qso 75 7 3 1 REPORT DATE 80 Q

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 DURING A PLANT TOUR TWO ICE CONDENSER INTERMEDIA K TO BE FROZEN SHUT. THIS CONSTITUTES AN INOPERABLE INTERMEDIATE DECK 4 DOOR DELINEATED IN TECH; SPEC. 3.6.5.3. THE ICE WAS CHIPPED OFF AND THE 6 DOORS WERE RETURNED TO AN OPERABLE STATUS.. PUBLIC HEALTH AND SAFETY

~o 6 WERE NOT JEOPARDIZED. NO PREVIOUS EVENTS OF THIS NATURE ARE KNOWN.

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~044 20 REVISION EVENT YEAR REPORT NO. CODE TYPE NO.

LERIRO 042 ERRORS 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDR PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~ZQSR ~ZQ\2 ~9Q2o ~902 0 0 LN1 Q22 LJLI024 ~N QEE N 1 2 0 QRS 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 0

1 BE DETERMINED. NEIGHBORING AIR CHILLERS WERE OPERATI G R FUTURE ACTIONS ARE PRESENTLY PLANNED.

3 4

80 7 8 9 FACILITY STATUS  % POWER OTHER STATUS ~

~3P METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 7

K 8 9 0 022 LOOOO l022 10 CONTENT 12 13 N A 44 MQSE 45 46 80 ACTIVITY RELEASED OF RELEASE AMOUNT OF ACTIVITY Q LOCATION OF RELEASE Q EKI MQ33 7 8 9 LZJ(S 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

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9 11 12

~ 0-13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 8

~00 9

0 11 Q40 12 N A 80 LOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION Z Q42 N A 7 8 9 10 80 O

ISSUED

~Q44 PUBLICITY DESCRIPTION ~ NRC USE ONLY 8 9 10 68 69 80 Ss NAME OF PREPARER M. S. BROWN PHPNEI 616-465-5901 Ext. 398

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