ML18219B523

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06/02/1978 Letter Licensee Event Report
ML18219B523
Person / Time
Site: Cook  American Electric Power icon.png
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: ML18219B523 (5)


Text

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+ines INDIANA& MICHIGANPOSER COMPANY DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 June 2, 1978 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 tjgense-DPR-74 Docke 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.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen R.F. Kroeger R. Kilburn R.J. Vollen BPI K.R. Baker RO:III R.C. Callen MPSC P.W. Steketee, Oi' 1978 Esq. JUH R. Walsh, Esq.

G. Charnoff, Esq.

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

Dir., MIPC (3 copies)

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7.77 )

LICENSEE EVENT REPORT

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,Q CONTROL BLOCK: (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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~01 7 8 9 M I D LICENSEE CODE D C 14 Qs 15 0 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 0 Qs 25 26

',4 I 1 LICENSE TYPE 1 I 30 04 I I 57 CAT 58 I Qs CON'T

~61 ~LQs 0 0 0 5 1 6 Q7 0 5 1 1 7 8 QB 0 6 0 2 7 8 Qe 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Qlo DURING NORMAL OPERATION,ON MAY 1 1 AND 14,1978,THE MAXN TURBINE STOP VALISE",D" CLOSURE LXMLT SWITCHBECAME INOPERABLE.TH IS SWXTCH PRO/ IDES 4 A TR XP S I G N AL L IS TE D IN T. S . TABLE 3 . 3 -, 1 I' EM 1 8, B, IN BOTH 0 C C A S 0 N S, I 4

0 6 THE APPLICABLE ACTION RENDU IREMENTS WERE FULFXLLED ~

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CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8

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7 FACILITY METHOD OF STATUS  % POWER OTHER STATUS

~30 - DISCOVERY DISCOVERY DESCRIPTION A32 ~

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80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ36 NA LOCATION OF RELEASE Q 6 ~Z Q33 Z Q34 NA 7 8 9 I0 II 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7,

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~00 0 111213 9

Q4 7 I Q4 4 N 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 7

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~00 0 Qs 9 II I2 NA 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 9 Z Q4 2 NA s 7 8 9 I0 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Q46 KZ W 8 9 Q44 I0 NA 68 69 80 o o

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1t NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION P-77I "UPDATE. REPORT - PREVIOUS REPORT ISSUED~25/78" LICENSEE EVENT REPORT CONTROL BLOCK: Ql (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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7 8 9 N I .D C LICENSEE'CODE C 2 14 Q20 15 0 0 0 0 0 LICENSE NUMBER 0 0 0 0 0 25 Qo 26 4 1 1 LICENSE TYPE 1 1 30 Q4~QE57 CAT 58 CON'T

~o 4 REPRRT SOURCE ~L m 0 5 0 0 0 3 1 6 Q,

0 3 2 2 7 8 Q, 0 6 0 2 7 8 Q, 7 8 68 69 EVENT DATE 74 75 REPORT DATE 80 60 61 DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10

~02 DURING THE INITIAL POWER TESTING PROGRAM, ROD POSITION INDICATION (RPI FOR ROD IN, EXCESS + 12 STEP LIMIT (T.S. 3.1.3.2) THREE TIMES

~O3 D-12 WAS FOUND TO BE OF THE 4 ON MARCH 22 and 23, 1978. ALSO ON MARCH 23, RPI FOR RODS H~2, P-8, F-10 AND K-10

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~o 6 WERE FOUND TO EXCEED THE T. S. LIMIT.

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

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Qll 11 E Q12 ~E 12 Q13 13 I N S T R U 18 Pl4 ~Y 19 Pl. ~Z 20 Pl.

QET LERIRO REPoRT ACTION FUTURE TAKEN EVENT YEAR

~78 21 ACTION'NPLANT 22 EFFECT 4

U 23 SHUTDOWN METHOD 24 SEQUENTIAL REPORT NO.

l0015 J 26 HOURS Ux 27 22 M

OCCURRENCE 28 ATTACHMENT SUBMITTED CODE 29 NPRDQ FORM SUB.

REPORT TYPE UL 30 PRIME COMP, SUPPLIER Ll 31 REVISION NO.

gl 32 COMPONENT MANUFACTURER 2

~EQ8~Z Qo ~Z Qo ~ZQEE 0 0 0 0 -

~Y Q23 ~> Q4 ~< Q25 11 Q28 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 o INVESTIGATION REVEALED THAT OF THE THREE EVENTS CONCERNING RP I FOR D-1 2 > TWO INVOLVED ADJUSTING THE SPAN ON THE CONDIT'IONING MODULE. APPARENTLY, ON THE REMAINING TWO EVENTS RPI HAD RETURNED TO WITHIN THE 12 STEP SPECIFICATION PRIOR TO INITIATING ANY REPAIR ACTION.

7 8 9 80 FACILITY STATUS 56 POWER OTHER STATUS Q'

~30 ~

METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 5

8 9 8 Q28 ~00 10 7

12 Q28 13 NA 44

~AQEE 45 46 OPERATOR OBSERVATION 80 7

6 ACTIVITY CONTENT RELEASED OF RElEASE

~Z Q33 ~ZQ34 AMOUNT OF ACTIVITY NA

~ NA LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION ~39

~l7 ~00 0 Q37 ~Q38 NA 80 7 8 9 11 12 13 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q42 7 8 9 10 4 80 o

PUBLICITY ISS17EED DESCRIPTION ~ NRC USE ONLY 2

7 8 9 10 68 69 80 ER 616-465-5901 0 NAME OF PREPARER Jack Rischling

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