05000316/LER-2078-059-03, Letter from Indiana & Michigan Power Co to NRC Submitting License Event Report RO 78-059/03L-0

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)

LER-2078-059, Letter from Indiana & Michigan Power Co to NRC Submitting License Event Report RO 78-059/03L-0

Event date:
Report date:
3162078059R03 - NRC Website

text

REGULATORY INFORMATION DISTRIBUTION SY TEM (RIDS>

DISTRIBUTION FOR lNCOMING MATERIAL 50-316 KEPPLER J G

ORG:

SIGNALLER 9

V IN S. MI PWR DOCD ATE: 09/05/78 DATE RCVD: 09/08/78

.YPE:

LETTER NOTARIZ

'r"JECT:

JRWARDING LICENSEE EVENT REACTOR PWR WAS INCREASED SPEC

4. 2. h.

1 LIMIT OF 94/

ED:

NO COPIES RECEIVED LTR 1

ENCL 1

REPT (RO 50-31e/78-059>

ON 08/06/78 CONCERNING ABOVE THE ADMINISTRATIVELlMIT OF 91/

AND THE TECH WITHOUT DETERMING THE AXIAL PWR DISTRIBUTION.

PLANT NAME: COOK UNlT 2 REVIEWER INITIAL:

XJM DISTRlBUTOR INITIAL:

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

1.

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

FOR ACTION:

BR CHIEF

~~

C4HtW/4

- NCL INTERNAL:

EXTERNAL:

.P E~~4W/2 ENCL I 0 C SYSTEMS BR++W/ENCL NOVAK/CHECK++W/ENCL AD FOR ENG>%W/ENCL HANAUER4~W/ENCL AD FOR SYS Cc PROJ++W/ENCL ENGINEERING BR4~%W/ENCL KREGER/J.

COLLINS+4W/ENCL K SEYFRIT/IE4%W/ENCL LPDR~S ST.

JOSEPH'I >+W/ENCL NSI C~~~W/ENCL ACRS CAT B+>W/16 ENCL NRC PDR~+W/ENCL MIPC4<W/3 ENCL EMERGENCY PLAN BR+~W/ENCL EEB~4W/ENCL PLANT SYSTEMS BR++W/ENCL AD FOR PLANT SYSTEMS44W/ENCL REACTOR SAFETY BR~wW/ENCL VOLLMER/BUNCI34~4 W/ENCL POWER SYS BR++W/ENCL DISTRIBUTION:

LTR 44 ENCL 44 S ZE:

iP ~1P

%%%%%%%%4%% ij 5f%%%%%4 4 4 ~k%%%%%%0M%%%

THE END CONTROL NBR:

78249024;

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~

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

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 A>>)

f1A C>

CA 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 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) p P,]978

I I

f t

i~

I II

~01']

7 CON'T [OO)]

7 8

CONTROL BLOCK:

9 LICENSEE CODE U. S. NUCLEAR REGULATORYCOMMISSION 1

LICENSEE EVENT,REPORT QI (PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION) 6 02 0

0 0

0 0

0' 0

0 0

0 Qs 4

1 1

1 1 04~0s 14 15 LICENSE NUMBER 25 26 LICENSE TYPE30 57 CAT 58 QB SOURCE LJQ Q

60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 10 REACTOR POWER WAS INCREASED ABOVE THE ADMINISTRATIVELIMIT 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

~OB 7

8

~10

~I SYSTEM

CAUSE

CAUSE COMP.

VALVE, CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

~ZZ 0>>

~AQn

~A" Qs Z

Z Z

Z Z

Z 0>4

~ZQ>s

~Z Qs 9

10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER(RP EVENT YEAR REPORT NO.

CODE TYPE NO.

0>>

Rsvos7

~78

~

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

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS

&22 SUBMITTED FORM SUB.

SUPPLIER MANUFACTURER

~HQs~HOs

~Z020

~ZQ 0

0 0

QO

~N Qss

~NQ4

~Z 025 Z

9 9

9 Qss 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 FAILURE OF THE UNIT SUPERVISOR TO TERMINATE THE POWER INCREASE AT 91/s.

THIS 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

THE APONS IS NOT FUNCTIONING.

7 8

9 FACILITY STATUS

'95 POWER 5

~EQss

~09 5

Qss 7

8 9

10 12 13 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITY~

~16 Z

Q33 Z

Q34 NA 7

8 9

10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~i'

~00 0 Qs7 Z Qss NA 7

I 8

9 11 12 13 4

PERSONNEL INJURIES 7,

8 9

11 12 LOSS OF OR DAMAGETO FACII.ITY Q43 TYPE

DESCRIPTION

s Z 04s NA 7

8 9

10 PUBLICITY ISSUED DESCRIPTIONQ ZO<

L~J~O44 NA 80 METHOD OF OTHER STATUS ~

DISCOVERY NA

'AQ31 44 45 46 DISCOVERY DESCRIPTION Q32 OPERATOR OBSERVATION 80 LOCATION OF RELEASE Q NA 45 80 80 80 80 NRC USE ONLY cu ss 80 ss 0

8 9

10 68 69 PHDNE (61 6) 465-5901 R.

S.

Lease NAME OF PREPARER USE THE P250 COMPUTER TO DETERMINE THE AXIAL POWER DISTRIBUTION FACTOR WHEN

0 3

1