ML18219E157

Submit Licensee Event Report Nos. RO 78-045/03L-0 & RO 78-046/03L-0

ML18219E157
Person / Time
Site:	Cook
Issue date:	08/14/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	James Keppler NRC/RGN-III
References
LER 1978-045-03L, LER 1978-046-03L
Download: ML18219E157 (8)

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REGULATORY INFORMATION DISTRIBUTION SYSTEM ( R IDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 08/14/78 NRC IN 4 MI PWR DATE RCVD: 08/17/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL FORWARDING LICENSEE EVENT REPT (RO 50-315/78-045) ON 07/15/78 CONCERNING QUADRANT TILT RATIO OF 1. 022 WAS EXHIBITED EXCEEDING LIMIT OF 1. 02 IDENTIFIED IN TECH SPEC 3. 2. 4. A... OCCURGNCE CAUSED BY A DAMPED XENON OSCILLATION... W/ATT LER78-046.

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

I 5 E 3 CYS ALL MATERIAL INCIDENT REPORTS (DISTRIBUTION CODE A002>

FOR ACTION: BR CHIEF ORBOi BC++W/4 ENCL INTERNAL: $ 9+'JJ - e+ I NRC PDR~~W/ENCL I E44.W/'NCL MIPC++W/3 ENCL I 5 C SYSTEMS BR++W/ENCL EMERGENCY PLAN BR>+W/ENCL NOVAK/CHECK44W/ENCL EEB~~W/ENCL, AD FOR ENG++W/ENCL PLANT SYSTEMS BR%>W/ENCL HANAUER++W/ENCL AD FOR PLANT SYSTEMS+%W/ENCL AD FOR SYS 8. PROJ+>W/ENCL REACTOR SAFETY BR44W/ENCL ENGINEERING BR+4W/ENCL VOLLMER/BUNCH4+W/ENCL KREGER/J. COLLINS++W/ENCL POWER SYS BR+<W/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR~S ST. JOSEPH MI++W/ENCL 7 I C. LIZ CARTER++M/ENCL NSIC~~W/ENCL ACRS CAT B44W/16 ENCL DISTRIBUTION: LTR 45 ENCL 45 CONTROL NBR: 78 190 42 I

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

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DONALD C. COOK NUCLEAR PLANT %D P.O. Box 458, Bridgman, Michigan 49106 CQ flv C )

fT'I I U August 14, 1978 c )ra chic~

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Mr. J.G. Keppler, Regional Director Wl Office of Inspection and Enforcement CA United States Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, IL 60137 mc'perating License DPR-58 Docket No. 50-315

Dear Mr. Keppler:

Pursuant to the requirements of the Appendix A Technical Specifications the following reports are submitted:

RO 78-045/03L-0 RO 78-046/03L-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.

G. Charnoff, Esq. AUG 3 j jg78 R. Walsh, 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)

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: 1, (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 04~

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[PPQ M I D C C 1 QR P 8 8 8 8 8 P 8 8 8 8 QR 4 1 1 1 1 30 57 CAT 58 QR 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 I.ICENSE TYPE CON'T REPRRT

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~o3 NHICH S IN EXCESS OF THE LIMKT GF 1 . 02 IDENTIFIED IN T . S . 3 . 2 ~ 4. A PCNFM LEVIK 4 REDUCTION FKM 62 PER CEÃZ KO 4 9 PER CENZ lEIAS PERFORMED BY 0 6 4 0 IN FULL CCMPLIANCE WITH T.S. 3.2.4 ACTION ITEN a.l.b.

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CODE 10 Q11 ~

CODE 11 Q12 SUBCODE

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COMPONENT CODE Z Z 5 5 Z 18 OCCURRENCE Q14 SUBCODE

~Z 19 REPORT Q16 SUBCODE

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28 ATTACHMENT COD6 29 NPRDP TYPE

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COMPONENT TAKEN ACTION ON PLANT METHOD HQURS ~22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER PJ018 33

&018 34 PJ028 35

~01 36 37 40 LI023 41 PJ024 42

&026 43 44 47 028 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o THE QUADRPKZ TILT g WHICH NAS DErTERMINED TO BE CAUSED BY A DAMPED XV'SCILLATION g NAS HIGH ONLY IN ONE QUADRANT WHICH RULEX) OUZ %K POSSIBILITY OF A DRDPPED RDD THE OSCILLATION FRY HAVE BEEN CAUSED BY AN ASSYMETRICAL BORON CONCEFZRATION IN THE 3

RCS ALTHOUGH THE DATA NAS NOZ SUFF C IEPZ PDR I A FULL DEZERMINAT ION . SUPPLIANT ATZACHED

~14 7 8 9 80 FACILITY METHOD OF STATUS 54 POWER OTHER STATUS QBO DISCOVERY DISCOVERY DESCRIPTION '32 8 9 F 028 ~86

'10 12 0<<

44 uBQ31 45 S

80 13 46 ACTIVITY CONTENT

~16 RELEASED OF RELEASE

~Z AMOUNT OF ACTIVITY NA Q LOCATION OF RELEASE Q Q33

~ZQ34 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION A3 1 ~00 p Q37 5 Q38 80 7 8 9 11 12 13 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY i 7 9

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ISSUED

'0 DESCRIPTION PUBLICITY DESCRIPTION Q43 NA NRC USE ONLY 80 oEr Q44 NA 7 8 9 10 68 69 80 o T. P. Beilman 616-465-5901 0

,NAME OF PREPARER PHONE

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ArIACHNEPl 'IO LEE 0 78-045/03L-0 SUPPLEMENT 'lO CAUSE D~PTICN PO'KR OPERATION ABOVE FIFTY PER CENT TWAS STARTED SUBSEQUENT K)

R1'TURGNG THE QUADRANT KMER TILT RATIO 1O WITHIN ITS LIMIT.

THE QUADRANT TILT RATIO WAS M3NITORED LVEHY HOUR FROM FIFTY PER CENT THERMAL POWER TO NINEXY-FIVE PER CENT POt'KR WITH

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7 77], 8 41 LtCENSEE EVENT REPORT j,/(

CONTROL BLOCK: Qi (PLEASE PRINT OR TYPE AL.L REQUIRED INFORMATION) 1 6

~87 N I D C C 1 Qs 0 O O 0 O O O O O O O 25 Os 26 LICENSE TYPE 30 Os~Os57 CAT 58 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER

'0 CON'T 8 5 0 0 3 1 5 0 7 1 9 7 8

~87 8 0 0 8 4 7 8 7 8 '0~LQ8 61 DOCKET NUMBER 68 Q7 69 EVENT DATE 74 Qs 75 1

REPORT DATE Qs EVENT DESCRIPTION AND PROBABLE CONSEQUENCES A10 WHILE IN t(ODE 1 It(8 INDICATED POSITION OF RODS H-lo, G-5, E-9, C-9, P-8 AND K-6

'NDICATED A DEVIATION OF GREATER THAN TWELVE S'JiPS FROM DEMAND POSITION. THIS IS IN

~O3 EXCESS OF 'QiE LIMIT IIKGSED BY T.S.3.1.3.2. SIMILAR

~O4 PREVIOUSLY SUBMITTED ARE 050 0315/76 13 F 44 AND 54 0315/77 27 F 28 i 33 AND 34

~OS 0315/78 04 07 38 i AND 050 0316/78 07 F 08 F 22 F 31 AND 41

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

~IE 10 Qtt 11 E Qs ~Z 12 Qts 13 I N S T R U 18 Q74 LiJQ78 19 LZJ 20 Qts SEQUENTIAL OCCURRENCE REPORT REVISION Q'7 LER/RO

<<>>87 ACTION FUTURE EVENT YEAR

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21 8

22 EFFECT

+23 SHUTDOWN

~04 24 REPORT NO.

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~03 28 ATTACHMENT CODE 29 NPRDC TYPE

+L 30 PRIME COMP.

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32 COMPONENT TAKEN ACTION i ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER 33 O78 ~KO78 34

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35

~808' 36 37 0 0 0 40 41 N On ~NOss ~NOn tt 1 I o On 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o THE CAUSE MRS TRAC1% 10 'IHE SIGNAL CONDITONING MODULES WHICH HAD DRIFXKD HIGH THE MODULES WERE RESPANNED AND THE INDICATED POSITIONS OF THE SIX KGS BETURNED'TO WITHIN SPECIFICATIONS. THE ROOT CAUSE OF THIS PROBLEM HAS NOT YEZ BEEN DEHXMINED ALTHOUGH AN ENGINEERING 81"VIEN IS W PROGR1MS.

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7 8 9 80 FACILITY STATUS 98 POWER OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

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Q28 ~10 10 0

12 Qss 13 44

~Q31 45 46 PERATIONAL EVZmt 80 ACTIVITY CONTENT 6

RELEASED OF RELEASE Z

AMOUNT OF ACTIVITY NA Q LOCATION OF RELEASE ~36

~Z Q33 Q34 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION QB 7 ~00 O Os>> Os 80 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 7

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0 11 Q40 12 NA, 80 lOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION 9 z Q42 7 8 9 10 80 O

ISSUED PUBLICITY LzJQ44 DESCRIPTION ~ NRC USE ONI.Y ocs 7 8 9 10 68 69 s 80 T- P- Beilman 616-465-.59 0 a

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