ML18219B564: Difference between revisions

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{{#Wiki_filter:0=s//~Pe REC: KEPPLFR J 6 NRC ORG: SI.IALLER D V IN 8(MI PWR REGULATORY INFORMATION DISTRIBUTION SYSTEM DISTRIBUTION FGR INCOMING MAT-RIAL<RIDS)50-316 DOCDATE: 08/l0/78 DATE RCVD: 08/l 5/78 DOCTYPE: LETTER NOTARIZED:
NO COPIES RECEIVED
 
==SUBJECT:==
LTR 1 ENCL LICENSEE EVENT REPT 50-3l6/78-5i ON.,07/li/78 CONCERNING DURING NORMAL OPERATION Tf)E APDMS WAS FOUND TQ BE INOPERABLE.
PLANT NAME: COOK-UNIT 2 REVIEWER INITIAL:,XBT DISTRIBUTOR INITIAL: RT~<<~<<H><<><<HHHH~%~+>+~~~
DISTR IBUT'ION OF THIS MATERIAL IS AS FOLLOWS NOTES: i.SEND 3 COPIES OF ALL MATERIAL TG IREE 1NCIDENT REPORTS<DISTRIBUTION CODE A002>FOR ACTION: 1NTERNAL: EXTERNAL: BR CHIEF GRBNi BC<<"+W/4 ENCL<EG>W/ENCL E~~W/2 ENCL I 5 C SYSTEMS BR<<~<<~W/ENCL NOVAK/CHECK<<~wW/
ENCL AD FOR ENG<<HI W/ENCL I IANAUER<<~<<~W/ENCI AD FOR SYS 5 PROJ<<l+W/ENCL ENGINEERING BR++W/ENCL KREGER/J.COLLINS+4W/ENCL K SEYFR IT/IE%+W/ENCL LPDR S ST.JOSEPH MI~~W/ENCL TIC, LI Z CARTERS<<~W/
ENCL NSIC<<~~WJENCL ACRS CAT BN%W/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<~M/ENCL REACTOR SAFETY BR++W/ENCL VOLLMER/BUNCH4+W/ENCL POWER SYS BR>+W/ENCL DISTRIBUTION:
-'TR 45 SI ZE: 3P ENCL 45 CONTROL NBR: 7822-0-8i%<<N<<(<<l<<Hl+%<<8<<Hf<<HHHHHI%%%%<<f<<INHHHl
<<t<<H$%%%THE END 4%4%%%%%%%%%%%
k<<l<<l+H%%%%%%%%%%H%%%
'4 t'~
DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 August 10, 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 w)fbi CI)C.i 4 I i tI 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 78-051/03L-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.CD Callen MPSC P.W.Steketee, Esq.G.Charnoff, Esq.'.'.Walsh, Esq.J.M.Hennigan G.Olson PNSRC J.F.Stietzel R.S.Keith T.P.Bei lman/J.L.Rischling Dir., IE (30 copies)Dir., MIPC (3 copies)AUG1a tgyg gV'M ft U.S.NUCLEAR REGULATORY COMMISSION NRC FORM 366 I7.77)LlCENSEE EVENT REPORT 1 5 CONTROL BLOCK: Q1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 4 I 6[oOQ M I 0 C C 2QEO 0 0 0 0 0 0 0 0 0 OQE 4 1 1 1 1QE~QE 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T~or""~LQR 0 5 0 0 0 3 1 6QT 0 7 1 1 7 8QR 0 8 1 0 7 8 Qg 7 8 60 61 DOCKETNUMBER 68 69 EVENT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10~02 DURING NOKSL OPERATION ON JULY ll THE APDNS liYAS FOUND TO BE INOPERABLE.
THE" FULL 74 75 REPORT DATE 4 D1HEZRINATION AS REQUIRED BY T.S.'~2~6~l.a.2.b.THE SEQUENCl&WAS MANUALLY RESET~03 LENQIH STEP CK&#xc3;Zl&HAD FAILED TO RESET THE SEQUENC1%WHICH INITIATES SCANS FOR F (Z)K)INITIATE THE REQUIRED SURVE3ILANCE.
INVESTIGATION REVEALl93 THAT ON JULY 9, THE 6 SE)QUENCER ALSO FAILED TO RESET, WHICH RESULTED IN MISSING THE SURVEILLANCE REQUIRED~07 BY T.S.4.2.6.l.a.2.b.
PREVIOUS INCLUDE RO-050-315/78-06.
~OB 7 8 9 80 7 8 SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE X Q11 X Q13~XQIE X X X X X.X QE~XQ15~Z Qs 9 10 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER)RP EVENT YEAR 1 REPORT NO.CODE TYPE NO.QIT REPoRT~78 Q~05 1 Q>~03 QL Q QO 21 22 23 24 26 27 28 29 30 31'2 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD.4 PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS+22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER
~BQIR~GQIg~ZQ35~ZQEI 0 0 0 0 Y Q33~NQ34~NQ35 W 1 2 O'Eg 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o, INVlDTIGATION REVl ALlX)THAT THE SEQUENClR FAILED TO RESET ONLY WHEN THE BANK D RODS WERE WITHDRAW NORE THAN 5 STEPS FKXI THE PREVIOUS RESET POSITION.DURING THE TIME THE STEP COUNTi&WAS KNCM TO BE OUT OF SERVICE ON JULY 11, THE T.S.REQUIRED SURVEILLANCES WERE OBTAINEED SATISFACTORILY e THE 0 MISSED SURVEILLMiKZ GN JULY 9 I 80 80 80 45 80 80 80 NRC USE ONLY Eg Eg 80 Eg 0 68'9 P o N E 6 1 6 4 6 5 59 0 1 4 4 WAS DISCOVlRED DURING THE INVESTIG'ATION OF THE JULY 1 1 4 EVENZ (SEE SUPPIElXENT) 7 8 9 FACILITY~30 METHOD OF STATUS 55POWER OTHER STATUS~DISCOVERY DISCOVERY DESCRIPTION Q32 CQ>L~J Gs~09 7 Qgg EOE~QE'8 9 10 12 13 44 45 , 46 ACTIVITY CONTENT RELEASED OF REI.EASE AMOUNT OF ACTIVITY~LOCATION OF RELEASE Q EKI Z Q LZJQ34 NA 7 8 9 10 44 PERSONNEL EXPOSURES~(P"'5'" o Q~VQ'"'""'EIIE 7 8 9 11 12 13 PERSONNEL INJURIES 7 8 9 11 1'2 LOSS OF OR DAMAGE TO FACILITY Q43 NA 7 8 9 10 P U 8 L I C I TY ISSUED DESCRIPTION
" 5~NQE4 NA 8 9 10 Jack Rischling 4~I'y ATTACHMENT TO LERg 78-051/03L-0 SUPPLE IENT K)CAUSE DESCRIPTION THE CAUSE'MRS FOUND TO BE A SET OF CXMFACTS ON THE K-8 RELAY IN THE ROD QONTROL IDGIC CABINETS.THIS RELAY IS NOW TEST1X)ON A&KhVQiLY BASIS NHEN AT KNKR, BY PHYSI~Y MOVING OUT THE BANK D RODS AND INStEGNG THAT THE APDHS FULL LENGTH STEP COUPZER RESETS THE%QUENGK.THIS FUNCTIONAL CHEXX HAS BEEN SATISFACTORILY CXMP~ON BOTH UNITS.}}

Revision as of 15:06, 16 August 2019

Letter from Indiana & Michigan Power Co to NRC Submitting Licensee Event Report (RO 78-051/03L-0)
ML18219B564
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 08/10/1978
From: Shaller D
American Electrtic Power System, Indiana Michigan Power Co
To: James Keppler
NRC/RGN-III
References
LER 1978-051-03L
Download: ML18219B564 (7)


Text

0=s//~Pe REC: KEPPLFR J 6 NRC ORG: SI.IALLER D V IN 8(MI PWR REGULATORY INFORMATION DISTRIBUTION SYSTEM DISTRIBUTION FGR INCOMING MAT-RIAL<RIDS)50-316 DOCDATE: 08/l0/78 DATE RCVD: 08/l 5/78 DOCTYPE: LETTER NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL LICENSEE EVENT REPT 50-3l6/78-5i ON.,07/li/78 CONCERNING DURING NORMAL OPERATION Tf)E APDMS WAS FOUND TQ BE INOPERABLE.

PLANT NAME: COOK-UNIT 2 REVIEWER INITIAL:,XBT DISTRIBUTOR INITIAL: RT~<<~<<H><<><<HHHH~%~+>+~~~

DISTR IBUT'ION OF THIS MATERIAL IS AS FOLLOWS NOTES: i.SEND 3 COPIES OF ALL MATERIAL TG IREE 1NCIDENT REPORTS<DISTRIBUTION CODE A002>FOR ACTION: 1NTERNAL: EXTERNAL: BR CHIEF GRBNi BC<<"+W/4 ENCL<EG>W/ENCL E~~W/2 ENCL I 5 C SYSTEMS BR<<~<<~W/ENCL NOVAK/CHECK<<~wW/

ENCL AD FOR ENG<<HI W/ENCL I IANAUER<<~<<~W/ENCI AD FOR SYS 5 PROJ<<l+W/ENCL ENGINEERING BR++W/ENCL KREGER/J.COLLINS+4W/ENCL K SEYFR IT/IE%+W/ENCL LPDR S ST.JOSEPH MI~~W/ENCL TIC, LI Z CARTERS<<~W/

ENCL NSIC<<~~WJENCL ACRS CAT BN%W/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<~M/ENCL REACTOR SAFETY BR++W/ENCL VOLLMER/BUNCH4+W/ENCL POWER SYS BR>+W/ENCL DISTRIBUTION:

-'TR 45 SI ZE: 3P ENCL 45 CONTROL NBR: 7822-0-8i%<<N<<(<<l<<Hl+%<<8<<Hf<<HHHHHI%%%%<<f<<INHHHl

<<t<<H$%%%THE END 4%4%%%%%%%%%%%

k<<l<<l+H%%%%%%%%%%H%%%

'4 t'~

DONALD C.COOK NUCLEAR PLANT P.O.Box 458, Bridgman, Michigan 49106 August 10, 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 w)fbi CI)C.i 4 I i tI 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 78-051/03L-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.CD Callen MPSC P.W.Steketee, Esq.G.Charnoff, Esq.'.'.Walsh, Esq.J.M.Hennigan G.Olson PNSRC J.F.Stietzel R.S.Keith T.P.Bei lman/J.L.Rischling Dir., IE (30 copies)Dir., MIPC (3 copies)AUG1a tgyg gV'M ft U.S.NUCLEAR REGULATORY COMMISSION NRC FORM 366 I7.77)LlCENSEE EVENT REPORT 1 5 CONTROL BLOCK: Q1 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 4 I 6[oOQ M I 0 C C 2QEO 0 0 0 0 0 0 0 0 0 OQE 4 1 1 1 1QE~QE 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T~or""~LQR 0 5 0 0 0 3 1 6QT 0 7 1 1 7 8QR 0 8 1 0 7 8 Qg 7 8 60 61 DOCKETNUMBER 68 69 EVENT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10~02 DURING NOKSL OPERATION ON JULY ll THE APDNS liYAS FOUND TO BE INOPERABLE.

THE" FULL 74 75 REPORT DATE 4 D1HEZRINATION AS REQUIRED BY T.S.'~2~6~l.a.2.b.THE SEQUENCl&WAS MANUALLY RESET~03 LENQIH STEP CKÃZl&HAD FAILED TO RESET THE SEQUENC1%WHICH INITIATES SCANS FOR F (Z)K)INITIATE THE REQUIRED SURVE3ILANCE.

INVESTIGATION REVEALl93 THAT ON JULY 9, THE 6 SE)QUENCER ALSO FAILED TO RESET, WHICH RESULTED IN MISSING THE SURVEILLANCE REQUIRED~07 BY T.S.4.2.6.l.a.2.b.

PREVIOUS INCLUDE RO-050-315/78-06.

~OB 7 8 9 80 7 8 SYSTEM CAUSE CAUSE COMP.VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE X Q11 X Q13~XQIE X X X X X.X QE~XQ15~Z Qs 9 10 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER)RP EVENT YEAR 1 REPORT NO.CODE TYPE NO.QIT REPoRT~78 Q~05 1 Q>~03 QL Q QO 21 22 23 24 26 27 28 29 30 31'2 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD.4 PRIME COMP.COMPONENT TAKEN ACTION ON PLANT METHOD HOURS+22 SUBMITTED FORM SUB.SUPPLIER MANUFACTURER

~BQIR~GQIg~ZQ35~ZQEI 0 0 0 0 Y Q33~NQ34~NQ35 W 1 2 O'Eg 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o, INVlDTIGATION REVl ALlX)THAT THE SEQUENClR FAILED TO RESET ONLY WHEN THE BANK D RODS WERE WITHDRAW NORE THAN 5 STEPS FKXI THE PREVIOUS RESET POSITION.DURING THE TIME THE STEP COUNTi&WAS KNCM TO BE OUT OF SERVICE ON JULY 11, THE T.S.REQUIRED SURVEILLANCES WERE OBTAINEED SATISFACTORILY e THE 0 MISSED SURVEILLMiKZ GN JULY 9 I 80 80 80 45 80 80 80 NRC USE ONLY Eg Eg 80 Eg 0 68'9 P o N E 6 1 6 4 6 5 59 0 1 4 4 WAS DISCOVlRED DURING THE INVESTIG'ATION OF THE JULY 1 1 4 EVENZ (SEE SUPPIElXENT) 7 8 9 FACILITY~30 METHOD OF STATUS 55POWER OTHER STATUS~DISCOVERY DISCOVERY DESCRIPTION Q32 CQ>L~J Gs~09 7 Qgg EOE~QE'8 9 10 12 13 44 45 , 46 ACTIVITY CONTENT RELEASED OF REI.EASE AMOUNT OF ACTIVITY~LOCATION OF RELEASE Q EKI Z Q LZJQ34 NA 7 8 9 10 44 PERSONNEL EXPOSURES~(P"'5'" o Q~VQ'"'""'EIIE 7 8 9 11 12 13 PERSONNEL INJURIES 7 8 9 11 1'2 LOSS OF OR DAMAGE TO FACILITY Q43 NA 7 8 9 10 P U 8 L I C I TY ISSUED DESCRIPTION

" 5~NQE4 NA 8 9 10 Jack Rischling 4~I'y ATTACHMENT TO LERg 78-051/03L-0 SUPPLE IENT K)CAUSE DESCRIPTION THE CAUSE'MRS FOUND TO BE A SET OF CXMFACTS ON THE K-8 RELAY IN THE ROD QONTROL IDGIC CABINETS.THIS RELAY IS NOW TEST1X)ON A&KhVQiLY BASIS NHEN AT KNKR, BY PHYSI~Y MOVING OUT THE BANK D RODS AND INStEGNG THAT THE APDHS FULL LENGTH STEP COUPZER RESETS THE%QUENGK.THIS FUNCTIONAL CHEXX HAS BEEN SATISFACTORILY CXMP~ON BOTH UNITS.