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)

Text

QglWs~i~~1 ng/~v/W REGULATORY INFORMATION DISTRIBUTION SYSTEM (R IDS)DISTRIBUTION FOR INCOMING MATERIAL 50-315 REC: KEPPLER J G NRC ORG: SHALLER D V IN 4 MI PWR DOCDATE: 08/14/78 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: INTERNAL: EXTERNAL: BR CHIEF ORBOi BC++W/4 ENCL$9+'JJ-e+I I E44.W/'NCL I 5 C SYSTEMS BR++W/ENCL NOVAK/CHECK44W/ENCL AD FOR ENG++W/ENCL HANAUER++W/ENCL AD FOR SYS 8.PROJ+>W/ENCL ENGINEERING BR+4W/ENCL KREGER/J.COLLINS++W/ENCL K SEYFRIT/IE++W/ENCL LPDR~S ST.JOSEPH MI++W/ENCL 7 I C.LI Z CARTER++M/ENCL NSIC~~W/ENCL ACRS CAT B44W/16 ENCL NRC PDR~~W/ENCL MIPC++W/3 ENCL EMERGENCY PLAN BR>+W/ENCL EEB~~W/ENCL, PLANT SYSTEMS BR%>W/ENCL AD FOR PLANT SYSTEMS+%W/ENCL REACTOR SAFETY BR44W/ENCL VOLLMER/BUNCH4+W/ENCL POWER SYS BR+<W/ENCL DISTRIBUTION:

LTR 45 ENCL 45 S I ZE: 1P+2P+1P THE END CONTROL NBR: 78 190 42 0'it, I DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 August 14, 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 I chic~gn Wl CA%D CQ fT'I U fl v C)c)ra l.8)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.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)AUG 3 j jg78 NRC FORM 366 U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK: 1, (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6[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 04~QR 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 I.ICENSE TYPE 30 57 CAT 58 CON'T REPRRT~L~

+L 8 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDP PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HQURS~22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER PJ018&018 PJ028~01 LI023 PJ024&026 028 33 34 35 36 37 40 41 42 43 44 47 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 I C IEPZ PDR A FULL DEZERMI NAT I ON.SUPPLIANT ATZACHED METHOD OF DISCOVERY uBQ31 S 45 46 45 T.P.Beilman ,NAME OF PREPARER~14 7 8 9 FACILITY STATUS 54 POWER OTHER STATUS QBO F 028~86 0<<8 9'10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q~16~Z Q33~ZQ34 NA 7 8 9" 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION A3 1~00 p Q37 5 Q38 7 8 9 11 12 13 PERSONNEL IN JURIES 7 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY Q43 TYPE DESCRIPTION 9~ZQ42 NA i 7 8 9'0 PUBLICITY~ISSUED DESCRIPTION Q44 NA 7 8 9 10 80 LOCATION OF RELEASE Q 80 80 80 80 PHONE 80 NRC USE ONLY Er o 80 o 0 68 69 616-465-5901 DISCOVERY DESCRIPTION '32 r I 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 U.S.NUCLEAR REGULATORY COMMISSION 8 Qi (PLEASE PRINT OR TYPE AL.L REQUIRED INFORMATION) 6 O O 0 O O O O O O O Os Os~Os LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 NRC FORM 366 (7 77], 41 LtCENSEE EVENT REPORT j,/(CONTROL BLOCK: 1~87 N I D C C 1 Qs 0 7 8 9 LICENSEE CODE 14 15 CON'T~87 8 8~LQ8 5 0 0 0 3 1 5 Q7 0 7 1 9 7 8 Qs 0 8 1 4 7 8 Qs 7 8'0 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE'0 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~O6~OB 7 8 9 80 7 8 MODULES WERE RESPANNED AND THE INDICATED POSITIONS OF THE SIX KGS BETURNED'TO WITHIN SYSTEM CAUSE CAUSE COMP., VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE~IE Qtt E Qs~Z Qts I N S T R U Q74 LiJQ78 LZJ Qts 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR REPORT NO.CODE TYPE NO.Q'7<<>>87~7.8+~04 6 Q~~03+L Q QO 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDC PRIME COMP.COMPONENT TAKEN ACTION i ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER O78~KO78~SO>>~808'0 0 0 N On~NOss~NOn tt 1 I o On 33 34 35 36 37 40 41 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 SPECIFICATIONS. THE ROOT CAUSE OF THIS PROBLEM HAS NOT YEZ BEEN DEHXMINED ALTHOUGH AN ENGINEERING 81"VIEN IS W PROGR1MS.~13 4 7 8 9 11 12 lOSS OF OR DAMAGE TO FACILITY 43 TYPE DESCRIPTION z Q42 9 10 PUBLICITY ISSUED DESCRIPTION ~LzJQ44 9 10 9 7 8 O 7 8 NAME OF PREPARER T-P-Beilman 7 8 9 FACILITY STATUS 98 POWER OTHER STATUS Q~l5~E Q28~10 0 Qss 7 8 9 10 12 13 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY Q 6~Z Q33 Z Q34 NA 7 8 9 10 11 44 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION QB 7~00 O Os>>Os 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41 8~00 0 Q40 NA, 80 80 45 80 80 80 80 NRC USE ONI.Y 68 69 616-465-.59 cs o s 80 0 a (5 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32~Q31 PERATIONAL EVZmt 45 46 LOCATION OF RELEASE~36 S\i t Ill~]f*,, I Ig