ML18219B556

Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Reports (RO 78-059/03L-1 and RO 78-060/03L-0)

ML18219B556
Person / Time
Site:	Cook
Issue date:	09/08/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co
To:	James Keppler NRC/RGN-III
References
LER 1978-059-03L, LER 1978-060-03L
Download: ML18219B556 (8)

Text

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REGULATORY IN& 'MATION DISTRIBUTION SYSTEM r~e.

<RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-316 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 09/Og/78 NRC IN 4 MI PWR DATE RCVD: 09/13/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT <RO 50-316/78-059) ON 08/06/78 CONCERNING REACTOR PWR WAS INCREASED ABOVE ADMINSTRATIVE LIMIT OF 91/ AND THE TECH SPEC

4. 2. 6. 1 LIMIT OF 94/ WITHOUT DETERMINING THE AXIAL PWR DISTRIBUTION FACTOR FZ

... W/ATT LER 78-060.

PLANT NAME: COOK UNIT 2 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:gP4P DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS NOTES:

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

FOR ACTION: BR EF ORBSi BC+>W/4 ENCL INTERNAL: G FILE /ENCL NRC PDR4~W/ENCL

/2 ENCL MIPC~~W/3 ENCL I 8c C SYSTEMS BR4>W/ENCL EMERGENCY PLAN BR>>W/ENCL NOVAK/CHECK+<W/ENCL EEB~~W/ENCL AD FOR ENG+>W/ENCL PLANT SYSTEMS BR+~W/ENCL HANAUER++W/ENCL AD FOR PLANT SYSTEMS4+W/ENCL AD FOR SYS 8c PROJ>+W/ENCL REACTOR SAFETY BR++M/ENCL ENGINEERING BR++M/ENCL VOLLMER/BUNCH~+A/ENCL KREGER/J. COLLINS++W/ENCL POWER SYS BR>+W/ENCL K SEYFRIT/IE44W/ENCL EXTERNAL: LPDR'S ST. JOSEPH MI+>W/ENCL NSIC+4W/ENCL ACRS CAT B4+W/16 ENCL 1

DISTRIBUTION: LTR 44 ENCL 44 CONTROL NBR: 78202005 I

S ZE: 1 P+ 1 P+2P THE END

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Pone~ a%i G~ysr'~fuANKSMKWSAXRQkVEESBMBIdE DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, Michigan 49106

~<~/7'eptember 8, 1978 Mr. J.G. Keppl er, Regional Di rector fi f Of ce o Inspection and En forcement r ~ IJ Egg C0

,=g p United States Nuclear Regulatory Commission Region I II g ~y Cl) fC'V 799 Roosevelt Road Glen Ellyn, IL 60137 Operating Li cense 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 78-059/03L-1 RO 78-060/03L-O.

Since rely, D.V; Shaller Plant Manager

/bab cc: J.E. Dolan R.W. Jurgensen R. F. Kroeger R. Ki 1 burn R.J. Yollen BPI K.R. Baker RO: III R.C. Callen MPSC P.W. Steketee, Esq.

G. Charnoff, Esq.

R. Walsh, Esq.

G. Olson J.M. Hennigan PNSRC J.F. Stietzel 782020052 R.S. Keith T.P. Bei lman/J.L. Rischling Dir., IE (30 copies)

Dir., MIPC (3 copies)

I 1

(7-77 I "UKUAlk Ktl - KKEVEUp K)VUlK)0VliltgzVIOIIS CONTROL BLOCK: Qi {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~o1 8 9 N I 0 LICENSEE CODE C C 2QE0 14 15 00 0 0 0 0 LICENSE NUNIBER 00 00QA 1111QELLJO25 26 I.ICENSE TYPE 30 57 CAT 58 CON'T soUROE LJO6 SO 61 0 5 0 0 0,3 DOCKET NUMBER 1 6 07 6 69 0 8 0 EVENT DATE 6 7 8 74 Q 75 0 9 0 RFPPRTPATE 8 7 8 80 Q

EVENT DESCRIPTION ANO PROBABLE CONSEQUENCFS QIO

~o2 REACTOR POWER WAS INCREASED ABOVE THE ADMINISTRATIVE LIMIT OF 91% AND THE TECH.

SPEC ~ 4. 2 6 ~ ~ 1 LIMIT OF 94'5 WITHOUT DETERMINING THE AXIAL POWER DISTRIBUTION FACTOR FZ. THE AXIAL POWER DISTRIBUTION MONITORING SYSTEMS 'WAS ENERGIZED AT

~DB 90K BUT FAILED TO FUNCTION. THE UNIT SUPERVISOR RECOGNIZED THIS AND HE g ATTEMPTED TO GET MANUAL .SCANS. BUT FAILED. HE ALSO FAILED TO INSTRUCT REACTOR

~o7 OPERATOR TO STOP POWER INCREASE. REACTOR POWER REACHED 955 BEFORE IT WAS

~DB RETURNED BELOW 91'X 7 8.9 80 SYSTEM CAUSE CAUSE COMP. VALVE 7 &

~~

9 CODE 10 Q>>

CODE

~A 11 QI2 SUBCOOE

~A 12 Qi3 SEOUENi'IAL 13 COMPONENT CODE OCCURRENCE 18 Q14 SUBCODE

~Z 19 REPORT QIS SUBCODE

~Z 20 Q16 REVISION QIT LERgRO REPoRT ACTION FUTURE EVENT YEAR

~IN 21 2'2 EFFECT

~

23 SHUTDOWN

~05 24 REPORT NO.

9 26

~~

27 28 ATTACHMENT CODE LOD3J 29 NPRD.4 TYPE LLJ 30 PRIME COMP.

~

31 32 NO.

L~J COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SVB. SUPPI.IER MANUFACTURER 33 QIB ~Q 34

~Q20 35

~Q21 36 ~

37 0 0 0 0 40

~N 41 Q23 ~NQ24 42

~Z 43 Q2s 44 Z 9 9 9 47 Q2B CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS Q27 o FAILURE OF THE UNIT SUPEPVISOR TO TERMINATE THE POWER INCREASE AT 91K. THIS

~ll INCIDENT HAS BEEN REVIEWED WITH THE UNIT SUPERVISOR AND THE SHIFT SUP RVIS R INVOLVED. A PROCEDURE CHANGE HAS BEEN ISSUED WHICH PERMITS THF OPERATOR TO 3 USE THE P250 COMPUTER TO DETERMINE THE AX IAl POWER DI STRI BUT ION FACTOR WHEN

~14 THE APDMS IS NOT FUNCTIONING.

7 8 9 80 FACILITY STATUS 5 POWER OTHER STATUS Q METHOD OF DISCOVERY 7 a 9 L~JQ>> ~SS 10 12 QEE 13 NA 44

~AQ31 45 OP ERATOR DISCOVERY DESCRIPTION Q32 OBSERVATION 80 ACTIVITY CONTENT REI.EASED OF RELEASE

~Z NA AMOUNTOF ACTIVITY Q NA LOCATION OF RELEASE Q Q33 ~ZQ34 a 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 8

~00 9

o 11 QET ~zQEE 12 13 NA 80 PERSONNEL INJURIES NUMBER OESCRIPTIONQ4 EE ~00 7 8 9 o Qo 11 12 eo LOSS OF OR DAMAGE.TO FACILITY TYPE DESCRIPTION Q43

~ZQRE NA 7 8 10 80 PUBLICITY O

ISSUED

~NQ44 NA OFSCRIPTION Q NRC USE ONLY 7 8 9 10 68 69 BO o R.S. LEASE (616) 465-5901 0 NAME OF PREPARER

I I<< ~ ~ 4<< ~ %8 ~ ~ I<<<<

LlCENSEE EVENT REPORT CONTROL BLOCK: QI ItPLEASE PRINT OR TYPE ALL REQUIRED INFORIVIATION) 1 6

~o> M I D C C 2Q2 0 0 0 0 0 0 0 0'0 7 8 9 LICENSEE CODE 14 LICENSE NUMBER LICENSE TYPE CON'T

,"3'<<,~LQR 0 6 0 0 0 Il 6 Q70 8 0 9 7 8 Q80 9 0 8 7 808 Qo 8 60 61 DOCKET NU!IIBER 68 69 =VENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO

~o2 'URING NORMAL OPERATION ON A DISCOVERED THAT THE APDMS COiWVZER FAILED TO PRINIOUZ AI<<L . THE F ~

(Z ) SCANS AS REQUIRED BY T.S.4.2.6.1. C8 THE AUGUST 9 EVE&2 HMm WAS REDUCED n) 90% NHILE ON THE g AUGUST 14 EVl>T TEg APDiJS COMPUTE& WAS PZHiRKD K) OPERATION LKKDIAZELY.

PREVIOUS OCCURRENCES OF A SDQZAR NACRE ~DE: 050-315/78-03,06, 76-34 316/78-48

~O

~OS 7 8 9 80 SYSTEM CAUSE CAUSE COL'lP. VALVE CODE CODE SUBCODE COMPO" 6" T CODE SUBCODF SUBCODE 7 8 9 10 Q"

11 E Q'3 ~GQI3 12 13 N S T R U Q4 18

~ZQ>>

19

~Zoo 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q'7 LERIRP RR<<oR7 ACTION FUTURE EVENT YEAR

~78 21 22 EFFECT

~

23 SHUTDOWN

~06 24 REPORT NO.

0 26

~~

27

~03 28 ACHMENT CODE 29 NPROQ TYPE

~L 30 7 PRIME COMP 31

~0 NO.

32 COMPONENT TAKEN ACTION ON PLANT METHOD ~oURS Q22 SUBMITTED FORM SUB. SUPDLIER MANUFACTURER QIB ~FQIB ~BQ2o ~zQ21 0 0 0 3 ~Y Q23 ~YQ24 ~NQ2s ~ 1 2 0 Q2B 33 34 36 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o INVESTIGATION REVEAIED THE CAUSE TD BE THE %PARS OAWRUIER. THE DZTECIDRS WERE PERFORMING THE SCANS PK)PEHLY. HCTAEVER 'DK DATA WAS NCIl'HIS RESULTED IN THE COi&VZER MISSING SOME F ~ Z CAZCULATIONS. A FAULTY CARD WAS'DEHIIFIED AND REPLACED. NO FURIHER ML'FUYCZZONS HAVE BEEN EXPERIENCED.

4 CHANGE HAS BEEN INITIATED TO INSTALL A lYODIFICATICN 1 7 S 7 8 9 80 FACILITY STATUS <<! POWER OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

~09 7

7 I 8 8

8

~E 9

Q38 ACTIVITY CONTENT RELEASED QF RELEASE

~Z 9

Q33 10 10 Z

PERSONNEL EXPOSURES Q34 11 7

12 Q39 13 NA AMOUNT OF ACTIVITY NA I 44 44

~BQ3I 46 46 RX7lINE OPERATOR CHECK LOCATION OF RFLEASE 80 NUIIIBER TYPE OESCRIPTIQ l QB

~77 F000 00JQ37 ~ZQ38 NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ4 7 8 9

~00 0 Q4o NA 11 12 80 LOSS OF OR DAIR IAQ6 TO FACII.ITY TYPE DESCRIPTION Q43

~ZQ42 NA

9. 10 60 n

ISSUED

~NQ44 PUBLICITY DESCRIPTION

~ NA NRC USE ONLY 4<<

9 10 68 69 &0 8<<

0 NAME OF PREPARER PHONE:

SUPPIZMENT TO LER 578-060/03L-0

)MICH WILL PROVXDE ON AUDIBLE ALARM ON THIS TYPE FAILURE.

~4 P ~ ~