ML18219B557

Letter from Indiana & Michigan Power Co to NRC Submitting License Event Report RO 78-059/03L-0

ML18219B557
Person / Time
Site:	Cook
Issue date:	09/05/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-059-03L
Download: ML18219B557 (6)

Text

REGULATORY INFORMATION DISTRIBUTION SY TEM (RIDS>

DISTRIBUTION FOR lNCOMING MATERIAL 50-316 SIGNALLER KEPPLER J G ORG: 9 V DOCD ATE: 09/05/78 IN S. MI PWR DATE RCVD: 09/08/78

.YPE: LETTER NOTARIZED: NO COPIES RECEIVED LTR 1 ENCL 1

, JECT:

'r" JRWARDING LICENSEE EVENT REPT (RO 50-31e/78-059> ON 08/06/78 CONCERNING REACTOR PWR WAS INCREASED ABOVE THE ADMINISTRATIVE LlMIT OF 91/ AND THE TECH SPEC 4. 2. h. 1 LIMIT OF 94/ WITHOUT DETERMING THE AXIAL PWR DISTRIBUTION.

PLANT NAME: COOK UNlT 2 REVIEWER INITIAL: X JM DISTRlBUTOR INITIAL:

OF THIS MATERIAL IS AS FOLLOWS Ql'ISTRIBUTION NOTE -:

1. SEND 3 COPIES OF ALL MATERIAL TO IS<E INCIDENT REPORTS (DISTRIBUTION CODE A002>

FOR ACTION: BR CHIEF ~~ C4HtW/4 -NCL INTERNAL: .P NRC PDR~+W/ENCL E~~4W/2 ENCL MIPC4<W/3 ENCL I 0 C SYSTEMS BR++W/ENCL EMERGENCY PLAN BR+~W/ENCL NOVAK/CHECK++W/ENCL EEB~4W/ENCL AD FOR ENG>%W/ENCL PLANT SYSTEMS BR++W/ENCL HANAUER4~W/ENCL AD FOR PLANT SYSTEMS44W/ENCL AD FOR SYS Cc PROJ++W/ENCL REACTOR SAFETY BR~wW/ENCL ENGINEERING BR4~%W/ENCL VOLLMER/BUNCI34~4 W/ENCL KREGER/J. COLLINS+4W/ENCL POWER SYS BR++W/ENCL K SEYFRIT/IE4%W/ENCL EXTERNAL: LPDR~S ST. JOSEPH'I >+W/ENCL NSI C~~~W/ENCL ACRS CAT B+>W/16 ENCL DISTRIBUTION: LTR 44 ENCL 44 CONTROL NBR: 78249024; S ZE: iP ~1P

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DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106 September 5, 1978 A>> )

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Mr. J.G. Keppler, Regional Director CA 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 report is submitted:

RO 78-059/03L-O.

Sincerely, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen R.F. Kroeger R. Kilburn R.J. Vollen BPI p P,]978 K.R. Baker RO:III R.C. Callen MPSC P.W. Steketee, Esq.

R. Walsh, Esq.

G. Charnoff, Esq.

G. Olson J.M. Hennigan PNSRC J.F. Stietzel R.S. Keith T.P. Beilman/J.L. Rischling Dir., IE (30 copies)

Dir., MIPC (3 copies)

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1 U. S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT, REPORT CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 6

~01']

7 9 LICENSEE CODE 14 02 15 0 0 0 0 0 0' LICENSE NUMBER 0 0 0 0 25 Qs 26 4 1 1 LICENSE 1

TYPE30 1 04~0s 57 CAT 58 CON'T

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7 8 SOURCE LJQ 60 61 DOCKET NUMBER 68 Q 69 EVENT DATE 74 75 REPORT DATE 80 QB EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 10 REACTOR POWER WAS INCREASED ABOVE THE ADMINISTRATIVE LIMIT OF 91% AND THE TEC.

~03 SPEC. 4. 2. 6. 1 LIMIT OF 941, WITHOUT DETERMINING THE AXIAL POWER DISTRIBUTION

~O4 FACTOR FZ. THE AXIAL POWER DISTRIBUTION MONITORING SYSTEM WAS ENERGIZED AT

~Os 90K BUT FAILED TO FUNCTION. THE UNIT SUPERVISOR RECOGNIZED THIS AND HE

~OB ATTEMPTED TO GET MANUAL SCANS BUT FAILED. HE ALSO FAILED TO INSTRUCT REACTOR OPERATOR TO STOP POWER INCREASE. REACTOR POWER REACHED 95% BEFORE IT WAS

~o B RETURNED BELOW 91%.

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

~OB 7 8 9

~ZZ 10 0>> ~AQn 11

~A" Qs 12 13 Z Z Z Z Z Z 18 0>4 ~ZQ>s 19

~Z 20 Qs SEQUENTIAL OCCURRENCE REPORT REVISION 0>>

LER(RP Rsvos7 FUTURE EVENT YEAR

~78 21 22 EFFECT

~ ~gg 23 SHUTDOWN 24 REPORT NO.

26 27 28 ATTACHMENT CODE 29 NPRDQ TYPE 30 PRIME COMP.

31 NO.

COMPONENT 32'CTION TAKEN ACTION ON PLANT METHOD HOURS &22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~HQs~HOs 33 34

~Z020 35

~ZQ 36 37 0 0 0 QO 40

~N 41 Qss ~NQ4 42

~Z 43 025 44 Z 9 9 9 47 Qss CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27

~10 FAILURE OF THE UNIT SUPERVISOR TO TERMINATE THE POWER INCREASE AT 91/s. THIS

~I INCIDENT HAS BEEN REVIEWED WITH THE UNIT SUPERVISOR AND THE SHIFT SUPERVISOR INVOLVED. A PROCEDURE CHANGE HAS BEEN ISSUED WHICH PERMITS THE OPERATOR TO 3 USE THE P250 COMPUTER TO DETERMINE THE AXIAL POWER DISTRIBUTION FACTOR WHEN THE APONS IS NOT FUNCTIONING.

7 8 9 80 5

FACILITY STATUS

~EQss ~09

'95 POWER 5 Qss OTHER STATUS NA

~ METHOD OF DISCOVERY

'AQ31 DISCOVERY DESCRIPTION Q32 OPERATOR OBSERVATION 7 8 9 10 12 13 44 45 46 80

~16 ACTIVITY Z Q33 CONTENT RELEASED OF RELEASE Z Q34 AMOUNTOF ACTIVITY NA

~ NA LOCATION OF RELEASE Q 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~i' 7 I 8

~00 9

0 Qs7 11 12 Z Qss 13 NA 4 80 PERSONNEL INJURIES 7, 8 9 11 12 LOSS OF OR DAMAGE TO FACI I.ITY 80 TYPE DESCRIPTION Q43 s Z 04s NA 7 8 9 10 80 PUBLICITY ISSUED DESCRIPTION Q NRC USE ONLY cu ss ZO< L~J~O44 NA 8 9 10 68 69 80 ss 465-5901 0 NAME OF PREPARER R. S. Lease PHDNE (61 6)

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