ML18219E153

Submit Licensee Event Report No. RO 78-050/03L-0

ML18219E153
Person / Time
Site:	Cook
Issue date:	09/18/1978
From:	Shaller D American Electrtic Power System, Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co)
To:	James Keppler NRC/RGN-III
References
LER 1978-050-03L
Download: ML18219E153 (5)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIBS>

DISTRIBUTION FOR INCOMING MATERIAL 50-"315 REC: KEPPLER J G ORG: SHALLER D V DOCDATE: 09/18/ 78 NRC IN o~ MZ PWR DATE RCVD: 09/22f78 DGCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT (RO 50-315/78-050> ON 06/02/78 CONCERNING THE BORON INJECTION Tl<ROTTLI:- VALVE POSITIONS WERE CHECKED PURSUANT TO TECH SPEC

. 4. 5. 2F2. AND WERE FOUND TG BE OUT OF ADJUSTMENT, AND WERE REPOSITIONEDi LEAVING THE VALVES WITI.I AN UNK PLANT NAME: COOK UNIT 1 REVIEWER INITIAL: XJM DISTRIBUTOR INITIAL:

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOW

'OTES:

I 5 E 3 CYS ALL MATERIAL INCIDENT REPORTS

( DISTRIBUTION CODE A002)

FOR ACTION: R CHIEF ORBOl BC4i<W/4 ENCL INTERNAL: iEG FIL- /ENCL NRC PDR4<W/ENCL I 8(

= "

g ENCLBR+4W/ENCL C SYSTEMS MIPC44W/3 ENCL EMERGENCY PLAN BR+<W/ENCL NOVAK/CI.IECK4+W/ENCL EEB>+W/ENCL AD FOR ENG~~4W/LNCL PLANT SYSTFMS BR<4W/ENCL ISANAUER~ ~~W/ENCL AD FOR PLANT SYSTEMS++W/ENCL AD FOR SYS 5 PRO J~~+Wf ENCL REACTOR SAFETY BR4+W/ENCL ENGINEERING BR+kW/ENCL VOLLMER/8UNCIR++W/ENCL KREGER/ J. COLL INS44W/ENCL POWER SYS BR4<W/ENCL K SEYFR IT/IE++W/ENCL EXTERNAL: LPDR S ST. 'JOSEPH M I +~W/ ENCL NSICu ~W/ENCL ACRS CAT B4+Wf 16 ENCL DISTRIBUTION: LTR 44 ENCL 44 CONTROL NBR: 7808102 4 SIZE: iP+iP+1P

%%%%4%4 4%%% 0$ %%4%4 4 4 4%%4%%%%%%% r>CF%8$ % THE END

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<Std DONALD C. COOK NUCLEAR PLANT P.O. Box 458, Bridgman, i%ichigan 49106

.C/lg>

September 18, 1978 C >

Dl CD Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement United States Nuclear Regulatory Commission Region III 799 Roosevel t Road Glen Ellyn, IL 60137 Operating License DPR-58 Docket No. 50-3l5

Dear Mr. Keppler:

Pursuant to the requirements of the Appendix A Technical Specifications the following report is submitted:

RO 78-050/03L-O.

S i n cere ly, D.V. Shaller Plant Manager

/bab cc: J.E. Dolan bcc: R.L. Dudding R.W. Jurgensen E.A. Smarrella R.F. Kroeger L.J. Matthias R. Kilburn D.D. Nelson R.J. Yollen BP.I 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 780S10264 RES. Keith T.P. Bei lman/J.L. Rischling Dir., IE (30 copies)

Dir., MIPC (3 copies)

i ~ 3<<4 4I4 ~& CF NRC FORM 366 NUCLEAR REGULATORY COMMISSION I7-77)',3' '

LlCENSEE EVENT REPORT CONTROL BLOCK: Qi (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I DCC1Q300000000000Q3<<1 6

M I 25 1 1 1Q4~O<<

30 57 CAT 58 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 26 LICFNSE TYPE 4

CON'T

~0.1 SQURCF ~L~E 0 5 0 0 0 3 1 5 7 0 6 0 2 7 8 6 0 9 1 8 7 8 Q9 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBASLE CONSEQUENCES Q10 CN 6-2-78 THE BORON Z42KZXCN THRCIZZLE VALVE POSITIONS WERE CSPEED PURSWKZ TO T.S. 4.5.2e2. DUE TO INCORRECZ TEST ACCEPZANCE CRITERIA, THE VALVE POSITICNS HERE

~Q4 DEZERMMKl. TO BE OUZ OF AD3USTPEiVZ PZK) WERE HEPOSITICHED, IZAVING THE VALVES WITH AN UKKCtiYN FLCN CAPMZTZ ~ THIS ERROR HAS NOZ DISCOVERED AND CORRECZED UTIL

~os 8-18-78. TEES ZS THE PIBST EVE4VZ OF THZS TYPE-

~OS 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCOOE COMPONENT CQOE SUBCQOE SUBCQOE

~sF A ~BOio v A L v ~zOis

~

~Q9 Qi Q3 E E 04 ~G Qis 7 8 9 10 11 12 13 18 19 20 REVISION

"""'LJ SEQUENTIAL OCCURRENCE REPORT ~

. O LER/RP EVENT YEAR 21 22 LJ 23

~0<<L~J 24 REPORT iVO.

26 27 28 CODE 29 TYPF ML 30 LJ 31 NO.

32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPROA PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~S~Q MQ 33 34 35 l.zJO 36 37 40 IZJO33 41

~O34 42

~VO<<s 43 W

44 1 I 0 Os 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o YZZE BOOT CASSE OF THE EVENT WS BEEN 3HTHZBOTED TO AN ENGZIV82&iV4G EBBOB <<<<HZCH RESULTED IN THE UZILIZATlCNOF INCORRECT TEST MCEPZKXCE CRITi~. UPCN DISCOVERY OF THE ERROR, THE SITUAL POSITICN OF EACH VALVE HAS DCCUI4KiVHZ), THEA'4 HEZURNED TO ITS CORRECT POSITICN. THE ACCEPIRZCE CRITERIA CMTAINED IN THE TEST HAS B~

COHERED VIA TEMPOEQHY CHANGE SiiEET.. ~ SUPPLEMENT.

~O 7 8 9 80 FACILITY STATUS ~s POWER OTHER STATUS t3 METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 CZ3I 5 LzJO 28 1 0 0 29 ~CQ31 45 46 INTERNAL INVESTIC~ICN 80 ACTIVITY CONTENT RELEASED OF REL'EASE AMOUNTOF ACTIVITYjD5 LOCATION QF RELEASE Q EKl wO wQ 7 8 9 10 44 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39

~00 0 Q37 Z Q33 NA 7 8 9 11 12 13 80 PERSONNEL INJURIES 9 11 12 80 LOSS OF QR OAMAGC TO FACILITY TYPE DESCRIPTION Q43 9 ~ZO<<3 NA 8 9 10 80 3

ISSUED

~NQ44 PUBLICITY DESCRIPTION ~ NRC USE ONLY

<<3 4

7 8 9 'IO 68 69 80 <<3 C' C 1V

SUPPL1~PZ 1O CAUSE DESCBIPTICN UPCN DISCOVER.'F THE VALVE POSZTIQNi ERFQR, THE ACTUAL POSITION QF. EB~

TEKEL'E VALVE WS CCCUMBKED AND FORVEDED 'ZQ SERVICE CORPORATION ENGZNEEBS FOR ANALYSIS.. 'QiRDDZ COBBESPC5DE'iiE ZT HIS BEEN INDICATED BY SEHVXCE COBPORATICN MGMZ26 THAT. ALTHCUCH 'IHE VALVE POSITIONS ÃEBE LESS THAN THAT NEHE CONSISTENT WZTH ~

REQUIRED TO FUIZILL THE TFMiNECAL SPx~CMIQN FECN HEQUIRWENTS, THEY SAHH'Y ANALYSIS.

AS THE ~T riVS, CAUSED BY SUPPLYING IKCORHECZ DATA K)R THE TEST CRITERIA, THE ERROR HAS BEEN DISCUSSED NITH ALL ENGMXRBIG PEBSQHKE ACCEPTANCE RE-EHPHASIZQlG THE NECESSITY FOR P~BMENG ACCURATE MK) THOROUGH R1>ELKS PRIOR TO DATA DZSTRZBVZXCN FOR PKCEXXJBE USE.

ADDZTICNALLYg OPEBATIQNS DEPART!KNT H~~iKE BESPCNSZBLE FOR TEST REVE".H MD SCG~ANCE HAVE BEEN BEZNSTBUCZED ZN THE BP05ZANCE OF REPORCZNG TEST RESULTS FOR INVESTIGAWCN AND COBBECZZQN.